Science.gov

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 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  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. 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...

  13. 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.

  14. 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...

  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. 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.

  1. 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.

  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 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.

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  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. 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…

  10. 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.

  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. 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.

  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. 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

  15. 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.

  16. 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

  17. 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)

  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. 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.

  5. 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.

  6. 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.

  7. 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.

  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. 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.

  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. 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.

  17. 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.

  18. 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.

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  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. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. 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

  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. 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.

  18. 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.

  19. 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.

  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. 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.

  4. 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.

  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, 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.

  11. 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.

  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. 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.

  14. 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.

  15. 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.

  16. 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.

  17. 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

  18. 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.

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. 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)

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. [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

  14. 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)

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. 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.

  20. 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

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  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. 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.

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  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. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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

  15. 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.

  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. 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.

  18. 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.

  19. 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.

  20. 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.

  1. 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

  2. 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

  3. 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

  4. 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.

  5. 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.

  6. 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.

  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. 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.

  9. 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.

  10. 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

  11. 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

  12. 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

  13. 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.

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  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. 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.

  2. 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.

  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. 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.

  5. 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.

  6. 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.

  7. 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.

  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.

  11. Atmospheric Radiation Measurement program climate research facility operations quarterly report January 1 - March 31, 2008.

    SciTech Connect

    Sisterson, D. L.

    2008-05-22

    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 January 1 - March 31, 2008, for the fixed sites. The AMF is being deployed to China and is not in operation this quarter. The second quarter comprises a total of 2,184 hours. The average as well as the individual site values exceeded our goal this quarter. The Site Access Request System is a web-based database used to track visitors to the fixed and mobile 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. FKB represents the AMF statistics for the Haselbach, Germany, past deployment in 2007. NIM represents the AMF statistics for the Niamey, Niger, Africa, past deployment in 2006. PYE represents just the AMF Archive statistics for the Point Reyes, California, past deployment in 2005. In addition, users who do not want to wait for data to be provided through the ACRF Archive can request a research account on the local site data system. The seven computers for the research accounts are located at the Barrow

  12. Unocal Parachute Creek Shale Oil Program. Environmental Monitoring Plan quarterly report. Third quarter, 1989. Report for 1 July-30 September 1989

    SciTech Connect

    Not Available

    1989-11-30

    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 support agreement included development of and 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 the project is to produce 10,000 barrels per day of syncrude from oil shale, using the Unishale B process. A description of Compliance activities completed during the quarter and copies of agency reports are given in the document. Supplemental sampling for industrial hygiene also is described.

  13. UNOCAL Parachute Creek Shale Oil Program. Environmental monitoring plan quarterly report. First quarter 1988. Report for 1 January-31 March 1988

    SciTech Connect

    Not Available

    1988-05-31

    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. This report describes ambient and source compliance data collected during the quarter, progress in performance monitoring, certification for air quality, monitoring audits, and initial industrial hygiene supplemental monitoring.

  14. Overview of the Savannah River reactor surveillance program

    SciTech Connect

    Sindelar, R.L.; Thomas, J.K.; Baumann, N.P.

    1991-01-01

    Preliminary radiation effects studies, now nearing completion, are based upon short-term irradiations in the High Flux Isotope Reactor (HFIR) and University of Buffalo Reactor (UBR). The purpose of these studies is to assess the impact of radiation effects on the performance and service life of Savannah River Site (SRS) reactor components. The SRS reactor surveillance program was simultaneously established in order to validate the results of these short-term irradiations under conditions more applicable to the SRS reactor components. The main conditions of interest include: temperature, moderator chemistry and neutron spectrum. The materials employed in both the surveillance and short-term irradiation programs were taken from the SRS R-reactor process piping and included base, weld, and heat-effected zone metal samples in both the C-L and L-C orientations. Test specimen types include tensile, Charpy V-notch, compact tension, constant extension rate test, and wedge-opening-load. A program schedule has been established for the irradiation and testing of surveillance specimens. The surveillance capsules are currently undergoing irradiation near the center of the SRS K-rector core and will remain in this location until their total fast fluence is equal to the current maximum reactor tank wall exposure. The bulk of the specimens will then be moved to blanket capsules at the edge of the core in order to track the wall exposure. A small portion of the specimens will be removed and tested, and a third group of specimens will be removed from the central core position after they have accumulated a thermal fluence 50% greater than the current maximum tank wall exposure. Specimen groups will be removed from the blanket capsules and tested periodically. Additional capsules may be inserted in order to generate flow fluence or high thermal to fast flux ratio data. 17 refs.

  15. Overview of the Savannah River reactor surveillance program

    SciTech Connect

    Sindelar, R.L.; Thomas, J.K.; Baumann, N.P.

    1991-12-31

    Preliminary radiation effects studies, now nearing completion, are based upon short-term irradiations in the High Flux Isotope Reactor (HFIR) and University of Buffalo Reactor (UBR). The purpose of these studies is to assess the impact of radiation effects on the performance and service life of Savannah River Site (SRS) reactor components. The SRS reactor surveillance program was simultaneously established in order to validate the results of these short-term irradiations under conditions more applicable to the SRS reactor components. The main conditions of interest include: temperature, moderator chemistry and neutron spectrum. The materials employed in both the surveillance and short-term irradiation programs were taken from the SRS R-reactor process piping and included base, weld, and heat-effected zone metal samples in both the C-L and L-C orientations. Test specimen types include tensile, Charpy V-notch, compact tension, constant extension rate test, and wedge-opening-load. A program schedule has been established for the irradiation and testing of surveillance specimens. The surveillance capsules are currently undergoing irradiation near the center of the SRS K-rector core and will remain in this location until their total fast fluence is equal to the current maximum reactor tank wall exposure. The bulk of the specimens will then be moved to blanket capsules at the edge of the core in order to track the wall exposure. A small portion of the specimens will be removed and tested, and a third group of specimens will be removed from the central core position after they have accumulated a thermal fluence 50% greater than the current maximum tank wall exposure. Specimen groups will be removed from the blanket capsules and tested periodically. Additional capsules may be inserted in order to generate flow fluence or high thermal to fast flux ratio data. 17 refs.

  16. AR and TD Fossil-Energy Materials Program. Quarterly progress report for the period ending March 31, 1983

    SciTech Connect

    Not Available

    1983-05-01

    The objective of the AR and TD Fossil-Energy Materials Program is to conduct research and developmet 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. Distribution is as shown on pages 439-446. Future reports will be issued on a quarterly basis to a similar distribution. We hope thie series of AR and TD Fossil Energy Materials Program quarterly progress reports will aid in the dissemination of information developed on the program.

  17. Parental education and the WHO neonatal G-6-PD screening program: a quarter century later.

    PubMed

    Kaplan, M; Hammerman, C; Bhutani, V K

    2015-10-01

    Neonatal screening for glucose-6-phosphate dehydrogenase (G-6-PD) deficiency in any population with a male frequency >3-5%, combined with parental education regarding the dietary, environmental and sepsis-related triggers for hemolysis was recommended by the WHO (World Health Organization) Working Group in 1989. As the aim of identifying G-6-PD deficiency in the newborn period is to avert or detect extreme hyperbilirubinemia developing at home, before the development of kernicterus, the parental role in identifying evolving icterus was considered integral to any screening program. Now, a quarter century after publication of this report, severe bilirubin neurotoxicity associated with G-6-PD deficiency continues to be encountered worldwide. Screening programs have not been universally introduced but several national or regional maternal child health programs have implemented neonatal G-6-PD screening. Some reports detail the role of parental education, based on the above mentioned principles, through a variety of audio-visual materials. The paucity of randomized controlled trials or validated evidence to demonstrate the effectiveness of the contribution of parental education fails to meet the ideal testable evidence-based approach. However, our review of the cumulative experience and evidence currently available does supply certain information reflecting a positive impact of screening programs combined with parental input. We propose that the current information is sufficient to continue to support and apply the Working Group's recommendations. In order not to waste unnecessary time available, data may be used in lieu of randomized trials to continue to recommend screening programs, as suggested, in high-risk regions. If the incidence of kernicterus associated with G-6-PD deficiency is to be diminished, G-6-PD screening in combination with parental explanation may be one instance in which the consensus approach suggested by the WHO Working Group, rather than reliance

  18. Integral Fast Reactor Program annual progress report, FY 1991

    SciTech Connect

    Not Available

    1992-06-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1991. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R&D.

  19. Integral Fast Reactor Program annual progress report, FY 1991

    SciTech Connect

    Not Available

    1992-06-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1991. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R D.

  20. Integral Fast Reactor Program annual progress report, FY 1994

    SciTech Connect

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, J.J.

    1994-12-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1994. Technical accomplishments are presented in the following areas of the IFR technology development activities: metal fuel performance; pyroprocess development; safety experiments and analyses; core design development; fuel cycle demonstration; and LMR technology R&D.

  1. Integral Fast Reactor Program. Annual progress report, FY 1992

    SciTech Connect

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

    1993-06-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1992. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R&D.

  2. Integral Fast Reactor Program. Annual progress report, FY 1993

    SciTech Connect

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

    1994-10-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1993. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R and D.

  3. Electric and hybrid vehicle program site operator program. Quarterly progress report, January 1995--March 1995

    SciTech Connect

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

    1995-08-01

    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 United States. Information is shared reciprocally with a thirteenth site, not under Program contract. The vehicles are operator-owned. The Mission Statement of the Site Operator Program includes three major activities: (1) Advancement of electric vehicle technologies; (2) Development of infrastructure elements necessary to support significant electric vehicle use; and (3) Increasing the awareness and acceptance of electric vehicles (EVs) by the public. The current participants in the Site Operator Program are shown. Table 1 indicates the EVs in each of the Site Operator fleets. Table 2 provides baseline information on several EVs currently in use by the Site Operators, or which have evolved to the point that they may be introduced in the near future. The Program is currently managed by personnel of the Electric and Hybrid Vehicle Program at the Idaho National Engineering Laboratory (INEL). The current principal management functions include: Coordination of Site Operator efforts in the areas of public awareness and infrastructure development (program-related meetings, and educational presentations).

  4. Atmospheric Radiation Measurement program climate research facility operations quarterly report July 1 - September 30, 2008.

    SciTech Connect

    Sisterson, D. L.

    2008-10-08

    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 July 1 - September 30, 2008, for the fixed sites. The AMF has been deployed to China, but the data have not yet been released. The fourth quarter comprises a total of 2,208 hours. The average exceeded our goal this quarter. The Site Access Request System is a web-based database used to track visitors to the fixed and mobile 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. HFE represents the AMF statistics for the Shouxian, China, deployment in 2008. FKB represents the AMF statistics for the Haselbach, Germany, past deployment in 2007. NIM represents the AMF statistics for the Niamey, Niger, Africa, past deployment in 2006. PYE represents just the AMF Archive statistics for the Point Reyes, California, past deployment in 2005. In addition, users who do not want to wait for data to be provided through the ACRF Archive can request a research account on the local site data system. The seven computers for the

  5. Reactor materials program process water piping: K Reactor indirect failure probability

    SciTech Connect

    Daugherty, W.L.

    1988-05-09

    The hypothetical maximum rate loss of coolant accident (LOCA) for the Savannah River Production Reactors is the abrupt double-ended guillotine break (DEGB) of a large process water pipe. This accident is not considered credible in light of the low applied stresses and the inherent ductility of the piping material. The Reactor Materials Program was initiated to provide the technical basis for an alternate, credible design basis accident. The major thrust of this program is to develop an alternate maximum rate LOCA by deterministic means. Additionally, the probability of a DEGB is being determined; to show that in addition to being mechanistically implausible, a DEGB is also highly improbable. The probability of a DEGB of the piping has been evaluated in two parts: failure by direct means, and indirectly-induced failure. Failure by direct means can be credibly postulated to occur as an undetected crack grows to the point of instability, causing a large pipe break. Indirect failure of the piping can be triggered by an earthquake which causes other reactor components or the reactor building to fall on the piping or pull it from its anchor points. The indirect failure of the piping in K reactor is the subject of this report. 5 refs.

  6. 78 FR 67153 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-July Through September 2013

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-08

    ... Services under sections 1102, 1871, 1902, and related provisions of the Social Security Act (the Act) and... system of transparency, public participation, and collaboration. Therefore, this quarterly...

  7. Electric and Hybrid Vehicle Program: Site Operation Program. Quarterly progress report, July--September 1995

    SciTech Connect

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

    1995-12-01

    The Site Operator Program has evolved substantially since its inception in response to the Electric Vehicle Research and Demonstration Act of 1976. In its original form, a commercialization effort was intended but this was not feasible for lack of vehicle suppliers and infrastructure. Nonetheless, with DOE sponsorship and technical participation, a few results (primarily operating experience and data) were forthcoming. The current Program comprises eleven sites and over 200 vehicles, of which about 50 are latest generation vehicles. DOE partially funds the Program participant expenditures and the INEL receives operating and maintenance data for the DOE-owned, and participant-owned or monitored vehicles, as well as Program reports. As noted elsewhere in this report, participants represent several widely differing categories: electric utilities, academic institutions, and federal agencies. While both the utilities and the academic institutions tend to establish beneficial relationships with the industrial community.

  8. Space reactor system and subsystem investigations: Assessment of technology issues for the reactor and shield subsystem, SP-100 Program

    NASA Astrophysics Data System (ADS)

    Atkins, D. F.; Lillie, A. F.

    1983-06-01

    Preliminary assessment was completed of nuclear technology as it relates to candidate reactor/shield subsystems for the SP-100 Program. The scope of the assessment was confined to the nuclear package (to the reactor and shield subsystems). Nine generic reactor subsystems were addressed for the assessment.

  9. Overview of the Lockheed Martin Compact Fusion Reactor (CFR) Program

    NASA Astrophysics Data System (ADS)

    McGuire, Thomas

    2015-11-01

    The Lockheed Martin Compact Fusion Reactor (CFR) Program endeavors to quickly develop a compact fusion power plant with favorable commercial economics and military utility. An overview of the concept and its diamagnetic, high beta magnetically encapsulated linear ring cusp confinement scheme will be given. The analytical model of the major loss mechanisms and predicted performance will be discussed, along with the major physics challenges. Key features of an operational CFR reactor will be highlighted. The proposed developmental path following the current experimental efforts will be presented. ©2015 Lockheed Martin Corporation. All Rights Reserved.

  10. Electric and Hybrid Vehicle Program, Site Operator Program. Quarterly progress report, January--March 1996

    SciTech Connect

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

    1996-08-01

    Goals of the site operator program include field evaluation of electric vehicles (EVs) in real-world applications and environments, advancement of electric vehicle technologies, development of infrastructure elements necessary to support significant EV use, and increasing the awareness and acceptance of EVs by the public. The site operator program currently consists of 11 participants under contract and two other organizations with data-sharing agreements with the program. The participants (electric utilities, academic institutions, Federal agencies) are geographically dispersed within US and their vehicles see a broad spectrum of service conditions. Current EV inventories of the site operators exceeds 250 vehicles. Several national organizations have joined DOE to further the introduction and awareness of EVs, including: (1) EVAmerica (a utility program) and DOE conduct performance and evaluation tests to support market development for EVs; (2) DOE, DOT, the Electric Transportation Coalition, and the Electric Vehicle Association of the Americas are conducting a series of workshops to encourage urban groups in Clean Cities (a DOE program) to initiate the policies and infrastructure development necessary to support large-scale demonstrations, and ultimately the mass market use, of EVs. Current focus of the program is collection and dissemination of EV operations and performance data to aid in the evaluation of real- world EV use. This report contains several sections with vehicle evaluation as a focus: EV testing results, energy economics of EVs, and site operators activities.

  11. Atmospheric Radiation Measurement program climate research facility operations quarterly report October 1 - December 31, 2006.

    SciTech Connect

    Sisterson, D. L.

    2007-03-14

    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 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. Table 1 shows the accumulated maximum operation time (planned uptime), the actual hours of operation, and the variance (unplanned downtime) for the period October 1 through December 31, 2006, for the fixed and mobile sites. Although the AMF is currently up and running in Niamey, Niger, Africa, the AMF statistics are reported separately and not included in the aggregate average with the fixed sites. The first quarter comprises a total of 2,208 hours. For all fixed sites, the actual data availability (and therefore actual hours of operation) exceeded the individual (and well as aggregate average of the fixed sites) operational goal for the first quarter of fiscal year (FY) 2007. 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. NIM represents the AMF statistics for the current deployment in Niamey, Niger, Africa. PYE represents the AMF statistics for the Point Reyes, California, past deployment in 2005. In addition, users who do not want to wait for data to be

  12. Field Verification Program for Small Wind Turbines: Quarterly Report for October-December 2000; 4th Quarter, Iss. No.3

    SciTech Connect

    Cardinal, J.

    2001-07-03

    This newsletter provides a brief overview of the Field Verification Program for Small Wind Turbines conducted out of the NWTC and a description of current activities. The newsletter also contains case studies of current projects.

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

    SciTech Connect

    Bradley, R.A.

    1981-12-01

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

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

    SciTech Connect

    Not Available

    1985-02-01

    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 1984 to 1988. 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.

  15. Advanced Research and Technology Development Fossil Energy Materials Program. Quarterly progress report for the period ending September 30, 1983

    SciTech Connect

    Not Available

    1983-11-01

    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 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.

  16. Ferrocyanide Safety Program. Quarterly report for the period ending March 31, 1994

    SciTech Connect

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

    1994-04-01

    Various high-level radioactive waste from defense operations has accumulated at the Hanford Site in underground storage tanks since the mid-1940s. During the 1950s, additional tank storage space was required to support the defense mission. To obtain this additional storage volume within a short time period, and to minimize the need for constructing additional storage tanks, Hanford Site scientists developed a process to scavenge {sup 137}Cs from tank waste liquids. In implementing this process, approximately 140 metric tons of ferrocyanide were added to waste that was later routed to some Hanford Site single-shell tanks. The reactive nature of ferrocyanide in the presence of an oxidizer has been known for decades, but the conditions under which the compound can undergo endothermic and exothermic reactions have not been thoroughly studied. Because the scavenging process precipitated ferrocyanide from solutions containing nitrate and nitrite, an intimate mixture of ferrocyanides and nitrates and/or nitrites is likely to exist in some regions of the ferrocyanide tanks. This quarterly report provides a status of the activities underway at the Hanford Site on the Ferrocyanide Safety Issue, as requested by the Defense Nuclear Facilities Safety Board (DNFSB) in their Recommendation 90-7. A revised Ferrocyanide Safety Program Plan addressing the total Ferrocyanide Safety Program, including the six parts of DNFSB Recommendation 90-7, was recently prepared and released in March 1994. Activities in the revised program plan are underway or have been completed, and the status of each is described in Section 4.0 of this report.

  17. Parachute Creek Shale Oil Program. Environmental Monitoring Plan, quarterly report, second quarter, April 1-June 30, 1990

    SciTech Connect

    Not Available

    1990-08-31

    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 socioeconomic impacts during the period 1986-1993. Phase I of this project is to produce 10,000 per day of syncrude from oil shale, using the Unishale B process. The report contains compliance monitoring results, copies of regulatory reports and independent audits performed on compliance air quality, water quality, and supplemental analytical programs.

  18. Long-term materials test program. Quarterly report, January-March 1983

    SciTech Connect

    1984-03-01

    Exposure of gas turbine materials to a PFBC effluent under the Long-Term Materials Test Program has reached 1507 hours. Unprotected nickel and cobalt base blade and vane alloys show susceptibility to hot corrosion at 1500/sup 0/F (gas temperature), 1300/sup 0/F, and 1100/sup 0/F (air-cooled pins). Precious metal aluminide and M (Co,Fe) CrAlY overlay coatings continue to show good resistance to corrosion above 1450/sup 0/F, but are susceptible to varying degrees of pitting attack between 1050 and 1300/sup 0/F. Significant erosion/corrosion degradation of both base alloys and protective coatings/claddings has been observed on airfoil specimens exposed at 1350/sup 0/F, 800 to 900 fps and dust loadings less than 100 ppM for 1085 hours. Corrosion predominately occurred in areas of direct particle impaction; i.e., leading edge and pressure surface, indicating an erosion/corrosion synergism. At gas velocities of 1200 to 1400 fps, a platinum-aluminide coated IN-738 pin experienced a metal recession rate of 8 mils/1000-hours. The PFBC facility continues to show excellent operational reliability, accumulating over 1100 test hours this quarter. The only concern from an operations standpoint is the gradual thinning of the in-bed heat exchanger tubing at a rate of about 5 mils/100 hours off the diameter.

  19. Decontamination systems information and research programs. Quarterly report, July 1--August 31, 1996

    SciTech Connect

    1997-07-01

    The US contains numerous hazardous waste sites. Many sites are on private land near operating units of various companies. An effort is being made to determine the conditions under which such sites can be remediated voluntarily. The objective of the project will be to first assess the interest and willingness of industry in the Kanawha River Valley, WV to participate in discussions that would lead toward voluntary cleanup activities. The second will be to implement the activities agreed upon by the interested parties. The project will first involve individual discussions with the industrial, government, and other organized groups in the area. These discussions will help determine the feasibility of organizing voluntary efforts. If the discussions indicate that conditions may be favorable for developing individual or group voluntary cleanup projects, a working group will be convened to establish the environmental goals of the project as well as the technical approach for achieving those goals. The projects for the 1996 WVU Cooperative Agreement are categorized into three task focus areas: Task 1.0 Contaminant Plume Containment and Remediation, Task 2.0 Cross Cutting Innovative Technologies, and Task 3.0 Small Business Support Program. Summaries of the accomplishments for the subtasks reporting under these categories during the third quarter, 1 July 96 through 30 September 96, are presented.

  20. Commercial nuclear waste research and development program. Quarterly report, October-December 1981

    SciTech Connect

    Hakl, A.R.

    1982-01-01

    This document is a report of activities performed by AESD-Nevada Operations in meeting task objectives of the Nevada Nuclear Waste Storage Investigations (NNWSI) planning documentation for Fiscal Year (FY) 1982. Significant activities were: Completion of a fuel assembly exchange was successfully in support of the Spent Fuel Test-Climax (SFT-C) Program; input was provided, in response to FY 1982 guidance, to DOE/NV and the Office of Nuclear Waste Isolation (ONWI) for a proposed co-located Generic Packaging Facility (GPF); in response to FY 1982 guidance, drafts were prepared of facility layouts, material and process flow charts, equipment requirements, costs, and schedules for packaging (at E-MAD) of 28 alternative configurations of defense high-level waste, disassembled spent fuel, and commercial high-level waste in support of a proposed Test and Evaluation Facility (TEF); and quarterly dry run operations for canister emplacement in a drywell and in the Hot Bay Transfer Pit using the Emplacement/Installation Vehicle (EIV).

  1. AR and TD Fossil Energy Materials Program. Quarterly progress report for the period ending December 31, 1983

    SciTech Connect

    Bradley, R.A.

    1984-03-01

    The objective of the AR and TD Fossil Energy Materials Program is to conduct reseach 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 to 1986 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.

  2. AR and TD Fossil Energy Materials Program. Quarterly progress report for the period ending September 30, 1984

    SciTech Connect

    Bradley, R.A.

    1984-11-01

    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 Progam 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 1983 to 1987. 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.

  3. LMFBR aerosol release and transport program. Quarterly progress report, July-September 1981

    SciTech Connect

    Kress, T.S.; Tobias, M.L.

    1982-01-01

    This report summarizes progress for the Aerosol Release and Transport Program sponsored by the Office of Nuclear Regulatory Research, Division of Accident Evaluation of the Nuclear Regulatory Commission for the period July-September 1981. Topics discussed include (1) preparations for under-sodium tests at the Fast Aerosol Simulant Test Facility, (2) progress in interpretation of Oak Ridge National Laboratory-Sandia Laboratory normalization test results, (3) U/sub 3/O/sub 8/ in steam (light-water reactor accident) aerosol experiments conducted in the Nuclear Safety Power Plant, (4) experiments on B/sub 2/O/sub 3/ and SiO/sub 2/ aerosols at the Containment Research Installation-II Facility, (5) fuel-melting tests in small-scale experimental facilities for the core-melt aerosol program, (6) analytical comparison of simple adiabatic nonlinear and linear analytical models of bubble oscillation phenomena with experimental data.

  4. Aerosol release and transport program. Quarterly progress report, October-December 1981. [LMFBR; PWR; BWR

    SciTech Connect

    Adams, R. E.; Tobias, M. L.

    1982-05-01

    This report summarizes progress for the Aerosol Release and Transport Program sponsored by the Nuclear Regulatory Commission's Office of Nuclear Regulatory Research, Division of Accident Evaluation, for the period October-December 1981. Topics discussed include (1) under-sodium tests in the Fuel Aerosol Simulant Test (FAST) Facility, (2) U/sub 3/O/sub 8/ and Fe/sub 2/O/sub 3/ in steam (light-water reactor accident) aerosol experiments in the Nuclear Safety Pilot Plant, (3) generation and characterization of cadmium and CdO aerosols in the basic aerosol experimental program, (4) core-melt tests of Zircaloy-clad fuel capsules, (5) initial results of a piston-model bubble oscillation code allowing liquid bypass, and (6) calculations with the UVABUBL code to compare with underwater and under-sodium period measurements in FAST experiments.

  5. University Reactor Instrumentation Program. Final report, 1990--1992

    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.

  6. Generation IV Reactors Integrated Materials Technology Program Plan: Focus on Very High Temperature Reactor Materials

    SciTech Connect

    Corwin, William R; Burchell, Timothy D; Katoh, Yutai; McGreevy, Timothy E; Nanstad, Randy K; Ren, Weiju; Snead, Lance Lewis; Wilson, Dane F

    2008-08-01

    Since 2002, the Department of Energy's (DOE's) Generation IV Nuclear Energy Systems (Gen IV) Program has addressed the research and development (R&D) necessary to support next-generation nuclear energy systems. The six most promising systems identified for next-generation nuclear energy are described within this roadmap. Two employ a thermal neutron spectrum with coolants and temperatures that enable hydrogen or electricity production with high efficiency (the Supercritical Water Reactor-SCWR and the Very High Temperature Reactor-VHTR). Three employ a fast neutron spectrum to enable more effective management of actinides through recycling of most components in the discharged fuel (the Gas-cooled Fast Reactor-GFR, the Lead-cooled Fast Reactor-LFR, and the Sodium-cooled Fast Reactor-SFR). The Molten Salt Reactor (MSR) employs a circulating liquid fuel mixture that offers considerable flexibility for recycling actinides and may provide an alternative to accelerator-driven systems. At the inception of DOE's Gen IV program, it was decided to significantly pursue five of the six concepts identified in the Gen IV roadmap to determine which of them was most appropriate to meet the needs of future U.S. nuclear power generation. In particular, evaluation of the highly efficient thermal SCWR and VHTR reactors was initiated primarily for energy production, and evaluation of the three fast reactor concepts, SFR, LFR, and GFR, was begun to assess viability for both energy production and their potential contribution to closing the fuel cycle. Within the Gen IV Program itself, only the VHTR class of reactors was selected for continued development. Hence, this document will address the multiple activities under the Gen IV program that contribute to the development of the VHTR. A few major technologies have been recognized by DOE as necessary to enable the deployment of the next generation of advanced nuclear reactors, including the development and qualification of the structural

  7. Short contact time direct coal liquefaction using a novel batch reactor. Quarterly technical progress report, September 15, 1995--January 15, 1996

    SciTech Connect

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

    1996-01-26

    The objective of this research is to optimize the design and operation of the bench scale batch reactor (SCTBR) f or 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.

  8. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report. October 1 - December 31, 2009.

    SciTech Connect

    D. L. Sisterson

    2010-01-12

    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 first quarter of FY 2010 for the North Slope Alaska (NSA) locale is 1,987.20 hours (0.90 x 2,208); for the Southern Great Plains (SGP) site is 2,097.60 hours (0.95 x 2,208); and for the Tropical Western Pacific (TWP) locale is 1,876.8 hours (0.85 x 2,208). The ARM Mobile Facility (AMF) deployment in Graciosa Island, the Azores, Portugal, continues; its 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 are the result of downtime (scheduled or unplanned) of the individual instruments. Therefore, data availability is directly related to

  9. Cooperative research program in coal liquefaction. Quarterly report, August 1, 1991--October 31, 1991

    SciTech Connect

    Huffman, G.P.

    1991-12-31

    This Quarterly Report on coal liquefaction research includes discussion in the areas of (1) Iron Based Catalysts for Coal Liquefaction; (2) Exploratory Research on Coal Conversion; (3) Novel Coal Liquefaction Concepts; (4) Novel Catalysts for Coal Liquefaction. (VC)

  10. AR and TD Fossil Energy Materials Program. Quarterly progress report for the period ending December 31, 1982

    SciTech Connect

    Not Available

    1983-02-01

    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. 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.

  11. FY 1990 environmental research programs for the Nevada Operations Office. Work plan and quarterly reports, first through fourth quarter reports

    SciTech Connect

    1990-11-01

    This work 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 and site mitigation plans; 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 activities. In addition to these, archaeological and other activities 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, derivative classification of DRI documents, and preparation of any special reports not included in the requirements of the individual projects.

  12. REACTOR PRESSURE VESSEL ISSUES FOR THE LIGHT-WATER REACTOR SUSTAINABILITY PROGRAM

    SciTech Connect

    Nanstad, Randy K; Odette, George Robert

    2010-01-01

    The Light Water Reactor Sustainability Program Plan is a collaborative program between the U.S. Department of Energy and the private sector directed at extending the life of the present generation of nuclear power plants to enable operation to at least 80 years. The reactor pressure vessel (RPV) is one of the primary components requiring significant research to enable such long-term operation. There are significant issues that need to be addressed to reduce the uncertainties in regulatory application, such as, 1) high neutron fluence/long irradiation times, and flux effects, 2) material variability, 3) high-nickel materials, 4)specimen size effects and the fracture toughness master curve, etc. The first issue is the highest priority to obtain the data and mechanistic understanding to enable accurate, reliable embrittlement predictions at high fluences. This paper discusses the major issues associated with long-time operation of existing RPVs and the LWRSP plans to address those issues.

  13. Novel bimetallic dispersed catalysts for temperature-programmed coal liquefaction. Quarterly technical progress report, July--September 1995

    SciTech Connect

    Song, Chunshan; Schmidt, E.; Schobert, H.H.

    1996-01-01

    Coal liquefaction involves cleavage of methylene, dimethylene and ether bridges connecting polycyclic aromatic units and the reactions of various oxygen functional groups. Here in this quarterly, we report on the hydrocracking of 4-(l-naphthylmethyl)bibenzyl in the presence of iron (Fe) catalysts and sulfur and residual wall catalytic effect. Catalytic hydrocracking of 4-(1-naphthylmethyl)bibenzyl (NMBB) predominantly yielded naphthalene and 4-methylbibenzyl. Various iron compounds were examined as catalyst precursors. Sulfur addition to most catalyst precursors led to substantially higher catalyst activity and higher conversion. NMBB was also treated with sulfur in the absence of iron compounds, in concentrations of 1.2-3.4 wt%, corresponding to the conditions present in reactions with added iron compounds. Increasing sulfur concentrations led to higher NMBB conversions. Furthermore, sulfur had a permanent effect on the reactor walls. A black sulfide layer formed on the surface which could not be removed mechanically. The supposed non-catalytic reactions done in the same reactor but after experiments with added sulfur showed higher conversions than comparable experiments done in new reactors. This wall catalytic effect can be reduced by treating the sulfided reactors with hydrochloric acid. The results of this work demonstrate the significant effect of sulfur addition and sulfur-induced residual wall effects on carbon-carbon bond cleavage and hydrogenation of aromatics.

  14. Nuclear Medicine Program progress report for quarter ending September 30, 1991

    SciTech Connect

    Knapp, F.F. Jr.; Ambrose, K.R.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Srivastava, P.C.; Hasan, A.; Lambert, C.R.; Lambert, S.J.; Rice, D.E.

    1992-02-01

    Rat tissue distribution properties of IQNP,'' a new radioiodinated cholinergic-muscarinic receptor antagonist, are described. IQNP is the acronym for 1-azabicyclo(2.2.2)oct-3-yl {alpha}-hydroxy-{alpha}-phenyl-{alpha}(1-iodo-1-propen-3-yl) acetate, which is an analogue of the QNB muscarinic antagonist in which the p-iodophenyl moiety has been replaced with the 1-iodo-1-propen-3-yl moiety. The radioiodinated IQNP analogue is easier to prepare in much higher yields than QNB and is thus a candidate for the evaluation of muscarinic receptors by external imaging techniques. Studies in rats demonstrated that IQNP shows high uptake in those cerebral regions rich in muscarinic receptors QNB-treatment of rats either 1 h before (pre) or 2 h after (post) administration of radioiodinated IQNP resulted in significant displacement or blocking of cerebral specific IQNP uptake (% dose/gm) in the cortex and striatum. These studies demonstrate that IQNP has specificity for the cholinergic-muscarinic receptor and is a good candidate for further studies. Also during this period, several agents developed in the ORNL Nuclear Medicine Program were supplied to Medical Cooperative Programs for collaborative studies including the iodine-125-labeled BMIPP and DMIPP fatty acid analogues and the IPM antibody labeling agent. Tin-117m and gold-199 were produced in the ORNL High Flux Isotope Reactor (HFIR) and supplied to the OHER-supported program in the Medical Department at Brookhaven National Laboratory to aid in their research until the re-start of the High Flux Brookhaven Reactor.

  15. Nuclear Medicine Program progress report for quarter ending September 30, 1991

    SciTech Connect

    Knapp, F.F. Jr.; Ambrose, K.R.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Srivastava, P.C.; Hasan, A.; Lambert, C.R.; Lambert, S.J.; Rice, D.E.

    1992-02-01

    Rat tissue distribution properties of ``IQNP,`` a new radioiodinated cholinergic-muscarinic receptor antagonist, are described. IQNP is the acronym for 1-azabicyclo[2.2.2]oct-3-yl {alpha}-hydroxy-{alpha}-phenyl-{alpha}(1-iodo-1-propen-3-yl) acetate, which is an analogue of the QNB muscarinic antagonist in which the p-iodophenyl moiety has been replaced with the 1-iodo-1-propen-3-yl moiety. The radioiodinated IQNP analogue is easier to prepare in much higher yields than QNB and is thus a candidate for the evaluation of muscarinic receptors by external imaging techniques. Studies in rats demonstrated that IQNP shows high uptake in those cerebral regions rich in muscarinic receptors QNB-treatment of rats either 1 h before (pre) or 2 h after (post) administration of radioiodinated IQNP resulted in significant displacement or blocking of cerebral specific IQNP uptake (% dose/gm) in the cortex and striatum. These studies demonstrate that IQNP has specificity for the cholinergic-muscarinic receptor and is a good candidate for further studies. Also during this period, several agents developed in the ORNL Nuclear Medicine Program were supplied to Medical Cooperative Programs for collaborative studies including the iodine-125-labeled BMIPP and DMIPP fatty acid analogues and the IPM antibody labeling agent. Tin-117m and gold-199 were produced in the ORNL High Flux Isotope Reactor (HFIR) and supplied to the OHER-supported program in the Medical Department at Brookhaven National Laboratory to aid in their research until the re-start of the High Flux Brookhaven Reactor.

  16. Integrated Data Collection Analysis (IDCA) Program — IDCA Quarterly Program Review, September 14 and 15, 2010

    SciTech Connect

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

    2012-02-07

    The IDCA conducted a program review at Los Alamos National Laboratory, September 14 and 15, 2010. The review was divided into three parts: 1) an update on the current status of the program, 2) an information exchange and discussion on technical details for current issues and future planning, and 3) a tour of the SSST testing facilities at LANL. The meeting started with an update from DHS by Laura Parker and a restating of some of the objectives of the Proficiency Test of which the IDCA is currently engaged. This update was followed by a discussion of some high level programmatic issues particularly about ways of communicating the overall goals of the IDCA to non-technical representatives. The final topic focused on the difficulty of releasing information, including the DHS approval process, ITAR, and open publication. Next JGR presented a technical summary of accomplishments, schedule, milestones, and future directions. These key points made were: 1) about 1/3 of the materials have been tested, 2) some participants are behind others causing a lag in report writing, 3) method reports have been assigned to various participants to speed up the process of reporting, 4) the SSST Compendium needs reformatting and restructuring, and 5) the Compendium needs a web site to house with access control. After the technical update, some of the Proficiency Test results were shown comparing data from the various laboratories. These results included comparisons of the RDX standard, KC/sugar mixtures (-100 mesh and as received), KC/dodecane, KP/Al, and KP/C. Impact, friction, ESD, and DSC results were the focus. All the participants were involved in these discussions. This report includes summary notes, presentations, and explanatory information.

  17. Nuclear Medicine Program progress report for quarter ending June 30, 1992

    SciTech Connect

    Ambrose, K.R.; Callahan, AP.; McPherson, D.W.; Mirzadeh, S.; Hasan, A.; Lambert, C.R.; Rice, D.E.; Srivastava, P.C.

    1992-08-01

    In this report the results of preliminary studies of pancreatic exocrine function in normal patients and volunteers by a simple urine analysis using a new iodine-131-labeled triglyceride are described. The new ORNL agent, 1,2-dipalmitoyl-3-((15-piodophenyl)pentadecan-l-oyl)-rac-glycerol (1,2-Pal-3-IPPA) was radiolabeled with iodine-131 and used in clinical studies in a collaborative program with the Clinic for Nuclear Medicine at the University of Bonn, Germany. The observed rapid urinary excretion of high levels of the orally administered test agent from patients corroborated results from initial studies conducted in laboratory animals (ORNL/TM-12110). In the initial group of normal volunteers and 11 patients with normal pancreatic function an average of 76 {plus_minus} 13.8% of the administered activity was excreted in the urine in 24 h. Studies will now also focus on evaluation of this agent in patients with pancreatic insufficiency. The reactor production of dysprosium-166 in the ORNL High Flux Isotope Reactor (HFIR) and the separation of carrier-free holmium-166 have also been pursued. Holmium-166 (t{sub {1/2}}226.4 h) decays with the emission of high energy beta particles and abundant secondary electrons and is thus of interest for various therapeutic applications. Four-day irradiation of {sup 165}Ho in the HFIR resulted in production of {sup 166}Ho with a specific activity of 7.25 mCi/mg. The formation of {sup 166}Ho by beta-decay of reactor-produced {sup 166}Dy was also evaluated. The specific activity of {sup 166}Dy for an 8-day HFIR irradiation was 3.5 mCi/mg. Preliminary results indicate that carrier-free {sup 166}Ho can be separated from the neutron-irradiated target by HNO{sub 3} elution from di-(2-ethylhexyl)phosphoric acid (HDEHP) impregnated glass beads.

  18. Nuclear Medicine Program progress report for quarter ending June 30, 1992

    SciTech Connect

    Ambrose, K.R.; Callahan, AP.; McPherson, D.W.; Mirzadeh, S.; Hasan, A.; Lambert, C.R.; Rice, D.E.; Srivastava, P.C.

    1992-08-01

    In this report the results of preliminary studies of pancreatic exocrine function in normal patients and volunteers by a simple urine analysis using a new iodine-131-labeled triglyceride are described. The new ORNL agent, 1,2-dipalmitoyl-3-((15-piodophenyl)pentadecan-l-oyl)-rac-glycerol (1,2-Pal-3-IPPA) was radiolabeled with iodine-131 and used in clinical studies in a collaborative program with the Clinic for Nuclear Medicine at the University of Bonn, Germany. The observed rapid urinary excretion of high levels of the orally administered test agent from patients corroborated results from initial studies conducted in laboratory animals (ORNL/TM-12110). In the initial group of normal volunteers and 11 patients with normal pancreatic function an average of 76 {plus minus} 13.8% of the administered activity was excreted in the urine in 24 h. Studies will now also focus on evaluation of this agent in patients with pancreatic insufficiency. The reactor production of dysprosium-166 in the ORNL High Flux Isotope Reactor (HFIR) and the separation of carrier-free holmium-166 have also been pursued. Holmium-166 (t{sub {1/2}}226.4 h) decays with the emission of high energy beta particles and abundant secondary electrons and is thus of interest for various therapeutic applications. Four-day irradiation of {sup 165}Ho in the HFIR resulted in production of {sup 166}Ho with a specific activity of 7.25 mCi/mg. The formation of {sup 166}Ho by beta-decay of reactor-produced {sup 166}Dy was also evaluated. The specific activity of {sup 166}Dy for an 8-day HFIR irradiation was 3.5 mCi/mg. Preliminary results indicate that carrier-free {sup 166}Ho can be separated from the neutron-irradiated target by HNO{sub 3} elution from di-(2-ethylhexyl)phosphoric acid (HDEHP) impregnated glass beads.

  19. Heavy-Section Steel Technology Program quarterly progress report for April-June 1980

    SciTech Connect

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

    1980-10-01

    The Heavy-Section Steel Technology Program is an engineering research activity conducted by the Oak Ridge National Laboratory for the Nuclear Regulatory Commission. 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 investigation focuses on the behavior and structural integrity of steel pressure vessels containing cracklike flaws. Current work is organized into five 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. Nozzle-corner cracks under combined pressure and thermal loadings are being analyzed. Mechanisms of damping in crack propagation are being studied. Irradiation of the first specimens in the Fourth HSST Irradiation Series continued, and impact tests of several Charpy specimens from the previous series were completed. Heat-treatment conditions for the next thermal shock test were selected, and preparation of the test cylinder was initiated. Work was initiated to develop a low-upper-shelf seam weld for intermediate test vessel V-8A, and facility planning for pressurized thermal shock tests continued. 16 refs., 29 figs., 11 tabs.

  20. Reactor materials program process water component failure probability

    SciTech Connect

    Daugherty, W. L.

    1988-04-12

    The maximum rate loss of coolant accident for the Savannah River Production Reactors is presently specified as the abrupt double-ended guillotine break (DEGB) of a large process water pipe. This accident is not considered credible in light of the low applied stresses and the inherent ductility of the piping materials. The Reactor Materials Program was initiated to provide the technical basis for an alternate, credible maximum rate LOCA. The major thrust of this program is to develop an alternate worst case accident scenario by deterministic means. In addition, the probability of a DEGB is also being determined; to show that in addition to being mechanistically incredible, it is also highly improbable. The probability of a DEGB of the process water piping is evaluated in two parts: failure by direct means, and indirectly-induced failure. These two areas have been discussed in other reports. In addition, the frequency of a large bread (equivalent to a DEGB) in other process water system components is assessed. This report reviews the large break frequency for each component as well as the overall large break frequency for the reactor system.

  1. Commercial nuclear waste research and development program. Quarterly report, January-March 1982

    SciTech Connect

    Hakl, A.R.

    1982-04-01

    The Westinghouse Advanced Energy Systems Division Nevada Operations, under contract to the US Department of Energy, provides trained personnel and services at the E-MAD Facility required for nuclear materials handling, packaging, data gathering, and other related activities in support of the Commercial Nuclear Waste Research and Development Programs. Support is provided to research programs, including: Waste packaging experiments, spent fuel test - Climax (SFT-C), Hanford Near Surface Test Facility (NSTF), Tests of spent reactor fuel interim handling and storage, tests to assess safety of transport systems for spent reactor fuel and solidified high level nuclear waste, and other special waste package development and handling tests as requested by the DOE. Activities reported have been performed to meet subtask objectives of the Nevada Nuclear Waste Storage Investigations (NNWSI) planning documentation for Fiscal Year 1982: Preliminary facility designs, process flow charts, and recommendations for equipment and services which would be required in a Generic Packaging Facility (GPF) co-located with the proposed Test and Evaluation Facility (TEF); E-MAD facility descriptions, logic diagrams, and process flow charts for E-MAD packaging of nuclear waste for the proposed TEF, if the TEF were not located on the Nevada Test Site; Preliminary cost estimates and schedules for a proposed large scale fuel storage demonstration, as requested by DOE/Headquarters; a remote source integrity check of the Cobalt 60 source; calibration and recertification of the Astro Arc automatic welding system. Installation of illustrated alarm panel for the E-MAD Remote Area Monitor (RAM) system in the E-MAD gatehouse; and installation of the RAM/CAM (Constant Air Monitoring) system computer interface hardware.

  2. Quarterly report on the Strontium Heat Source Development Program, Operations and By-Products Utilization Division for April-June 1981

    SciTech Connect

    Fullam, H.T.

    1981-09-01

    All experimental activities related to the Strontium Heat Source Development Program have been completed. The only remaining activities are preparation and issuance of final reports that summarize program results. This report represents the last of the program quarterly progress reports that will be issued.

  3. Materials Inventory Database for the Light Water Reactor Sustainability Program

    SciTech Connect

    Kazi Ahmed; Shannon M. Bragg-Sitton

    2013-08-01

    Scientific research involves the purchasing, processing, characterization, and fabrication of many sample materials. The history of such materials can become complicated over their lifetime – materials might be cut into pieces or moved to various storage locations, for example. A database with built-in functions to track these kinds of processes facilitates well-organized research. The Material Inventory Database Accounting System (MIDAS) is an easy-to-use tracking and reference system for such items. The Light Water Reactor Sustainability Program (LWRS), which seeks to advance the long-term reliability and productivity of existing nuclear reactors in the United States through multiple research pathways, proposed MIDAS as an efficient way to organize and track all items used in its research. The database software ensures traceability of all items used in research using built-in functions which can emulate actions on tracked items – fabrication, processing, splitting, and more – by performing operations on the data. MIDAS can recover and display the complete history of any item as a simple report. To ensure the database functions suitably for the organization of research, it was developed alongside a specific experiment to test accident tolerant nuclear fuel cladding under the LWRS Advanced Light Water Reactor Nuclear Fuels Pathway. MIDAS kept track of materials used in this experiment from receipt at the laboratory through all processes, test conduct and, ultimately, post-test analysis. By the end of this process, the database proved to be right tool for this program. The database software will help LWRS more efficiently conduct research experiments, from simple characterization tests to in-reactor experiments. Furthermore, MIDAS is a universal tool that any other research team could use to organize their material inventory.

  4. Light Water Reactor Sustainability Program: Reactor Safety Technologies Pathway Technical Program Plan

    SciTech Connect

    Corradini, M. L.

    2015-06-01

    In the aftermath of the March 2011 multi-unit accident at the Fukushima Daiichi nuclear power plant (Fukushima), the nuclear community has been reassessing certain safety assumptions about nuclear reactor plant design, operations and emergency actions, particularly with respect to extreme events that might occur and that are beyond each plant’s current design basis. Because of our significant domestic investment in nuclear reactor technology (99 operating reactors in the fleet of commercial LWRs with five under construction), the United States has been a major leader internationally in these activities. The U.S. nuclear industry is voluntarily pursuing a number of additional safety initiatives. The NRC continues to evaluate and, where deemed appropriate, establish new requirements for ensuring adequate protection of public health and safety in the occurrence of low probability events at nuclear plants; (e.g., mitigation strategies for beyond design basis events initiated by external events like seismic or flooding initiators). The DOE has also played a major role in the U.S. response to the Fukushima accident. Initially, DOE worked with the Japanese and the international community to help develop a more complete understanding of the Fukushima accident progression and its consequences, and to respond to various safety concerns emerging from uncertainties about the nature of and the effects from the accident. DOE R&D activities are focused on providing scientific and technical insights, data, analyses methods that ultimately support industry efforts to enhance safety. These activities are expected to further enhance the safety performance of currently operating U.S. nuclear power plants as well as better characterize the safety performance of future U.S. plants. In pursuing this area of R&D, DOE recognizes that the commercial nuclear industry is ultimately responsible for the safe operation of licensed nuclear facilities. As such, industry is considered the primary

  5. Water cooled breeder program summary report (LWBR (Light Water Breeder Reactor) development program)

    SciTech Connect

    Not Available

    1987-10-01

    The purpose of the Department of Energy Water Cooled Breeder Program was to demonstrate pratical breeding in a uranium-233/thorium fueled core while producing electrical energy in a commercial water reactor generating station. A demonstration Light Water Breeder Reactor (LWBR) was successfully operated for more than 29,000 effective full power hours in the Shippingport Atomic Power Station. The reactor operated with an availability factor of 76% and had a gross electrical output of 2,128,943,470 kilowatt hours. Following operation, the expended core was examined and no evidence of any fuel element defects was found. Nondestructive assay of 524 fuel rods determined that 1.39 percent more fissile fuel was present at the end of core life than at the beginning, proving that breeding had occurred. This demonstrates the existence of a vast source of electrical energy using plentiful domestic thorium potentially capable of supplying the entire national need for many centuries. To build on the successful design and operation of the Shippingport Breeder Core and to provide the technology to implement this concept, several reactor designs of large breeders and prebreeders were developed for commercial-sized plants of 900--1000 Mw(e) net. This report summarizes the Water Cooled Breeder Program from its inception in 1965 to its completion in 1987. Four hundred thirty-six technical reports are referenced which document the work conducted as part of this program. This work demonstrated that the Light Water Breeder Reactor is a viable alternative as a PWR replacement in the next generation of nuclear reactors. This transition would only require a minimum of change in design and fabrication of the reactor and operation of the plant.

  6. Severe accident sequence assessment for boiling water reactors: program overview

    SciTech Connect

    Fontana, M. H.

    1980-10-01

    The Severe Accident Sequence Assessment (SASA) Program was started at the Oak Ridge National Laboratory (ORNL) in June 1980. This report documents the initial planning, specification of objectives, potential uses of the results, plan of attack, and preliminary results. ORNL was assigned the Brown's Ferry Unit 1 Plant with the station blackout being the initial sequence set to be addressed. This set includes: (1) loss of offsite and onsite ac power with no coolant injection; and (2) loss of offsite and onsite ac power with high pressure coolant injection (HPCI) and reactor core isolation cooling (RCIC) as long as dc power supply lasts. This report includes representative preliminary results for the former case.

  7. Educational Technology Program. Quarterly Technical Summary, 1 September Through 30 November 1972.

    ERIC Educational Resources Information Center

    Frick, Frederick C.

    Several on-goint activities were conducted during this quarter. Field trials of the Lincoln Training System-3 (LTS-3) at Keesler Air Force Base were extended to include high-aptitude students previously excluded. Results showed such students scored significantly higher on achievement tests and learned substantially faster when they received LTS…

  8. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report. October 1 - December 31, 2010.

    SciTech Connect

    Sisterson, D. L.

    2011-02-01

    Individual raw datastreams from instrumentation at the Atmospheric Radiation Measurement (ARM) Climate Research Facility 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 ARM Archive, where they are made available to users. For each instrument, we calculate the ratio of the actual number of processed data records received daily at the Archive to the expected number of data records. The results are tabulated by (1) individual datastream, 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 first quarter of FY2010 for the Southern Great Plains (SGP) site is 2097.60 hours (0.95 x 2208 hours this quarter). The OPSMAX for the North Slope Alaska (NSA) locale is 1987.20 hours (0.90 x 2208) and for the Tropical Western Pacific (TWP) locale is 1876.80 hours (0.85 x 2208). The first ARM Mobile Facility (AMF1) deployment in Graciosa Island, the Azores, Portugal, continued through this quarter, so the OPSMAX time this quarter is 2097.60 hours (0.95 x 2208). The second ARM Mobile Facility (AMF2) began deployment this quarter to Steamboat Springs, Colorado. The experiment officially began November 15, but most of the instruments were up and running by November 1. Therefore, the OPSMAX time for the AMF2 was 1390.80 hours (.95 x 1464 hours) for November and December (61 days). The differences in OPSMAX performance reflect the complexity of local logistics and the frequency of extreme weather events. It

  9. Damage analysis and fundamental studies. Quarterly progress report, October-December 1980

    SciTech Connect

    Not Available

    1981-02-01

    This report is the twelfth in a series of Quarterly Technical Progress Reports on Damage Analysis and Fundamental Studies (DAFS) which is one element of the Fusion Reactor Materials Program, conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The first eight reports in this series were numbered DOE/ET-0065/1 through 8.

  10. Program for studying fundamental interactions at the PIK reactor facilities

    NASA Astrophysics Data System (ADS)

    Serebrov, A. P.; Vassiljev, A. V.; Varlamov, V. E.; Geltenbort, P.; Gridnev, K. A.; Dmitriev, S. P.; Dovator, N. A.; Egorov, A. I.; Ezhov, V. F.; Zherebtsov, O. M.; Zinoviev, V. G.; Ivochkin, V. G.; Ivanov, S. N.; Ivanov, S. A.; Kolomensky, E. A.; Konoplev, K. A.; Krasnoschekova, I. A.; Lasakov, M. S.; Lyamkin, V. A.; Martemyanov, V. P.; Murashkin, A. N.; Neustroev, P. V.; Onegin, M. S.; Petelin, A. L.; Pirozhkov, A. N.; Polyushkin, A. O.; Prudnikov, D. V.; Ryabov, V. L.; Samoylov, R. M.; Sbitnev, S. V.; Fomin, A. K.; Fomichev, A. V.; Zimmer, O.; Cherniy, A. V.; Shoka, I. V.

    2016-05-01

    A research program aimed at studying fundamental interactions by means of ultracold and polarized cold neutrons at the GEK-4-4' channel of the PIK reactor is presented. The apparatus to be used includes a source of cold neutrons in the heavy-water reflector of the reactor, a source of ultracold neutrons based on superfluid helium and installed in a cold-neutron beam extracted from the GEK-4 channel, and a number of experimental facilities in neutron beams. An experiment devoted to searches for the neutron electric dipole moment and an experiment aimed at a measurement the neutron lifetime with the aid of a large gravitational trap are planned to be performed in a beam of ultracold neutrons. An experiment devoted to measuring neutron-decay asymmetries with the aid of a superconducting solenoid is planned in a beam of cold polarized neutrons from the GEK-4' channel. The second ultracold-neutron source and an experiment aimed at measuring the neutron lifetime with the aid of a magnetic trap are planned in the neutron-guide system of the GEK-3 channel. In the realms of neutrino physics, an experiment intended for sterile-neutrino searches is designed. The state of affairs around the preparation of the experimental equipment for this program is discussed.

  11. Electric and hybrid vehicle program, site operator program quarterly progress report for April through June 1996 (third quarter of fiscal year 1996)

    SciTech Connect

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

    1997-01-01

    The US Department of Energy (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. The goals of the Site Operator Program include the field evaluation of electric vehicles (EVs) in real-world applications and environments; the advancement of electric vehicle technologies; the development of infrastructure elements necessary to support significant electric vehicle use; and increasing the awareness and acceptance of EVs by the public. The Site Operator Program currently consists of eleven participants under contract and two other organizations that have data-sharing agreements with the Program (Table ES-1). Several national organizations have joined DOE to further the introduction and awareness of electric vehicles, including: (1) EVAmerica (a utility program) and DOE conduct performance and evaluation tests to support market development for electric vehicles; and (2) DOE, the Department of Transportation, the Electric Transportation Coalition, and the Electric Vehicle Association of the Americas are conducting a series of workshops to encourage urban groups in Clean Cities (a DOE program) to initiate the policies and infrastructure development necessary to support large-scale demonstrations, and ultimately the mass market use, of electric vehicles. The current focus of the Program is the collection and dissemination of EV operations and performance data to aid in the evaluation of real-world EV use. This report contains several sections with vehicle evaluation as a focus.

  12. Library Service Enhancement Program. Second Quarterly Progress Report to the Council on Library Resources for the Period December 1, 1977-February 28, 1978.

    ERIC Educational Resources Information Center

    Harrison, Orion

    This progress report presents information on a comprehensive program that involved the library in all aspects of the academic program. During the second quarter, meetings with the faculty were completed and weekly meetings were held with the Director of Libraries and the Associate Director for Operations. Since meaningful contacts with students…

  13. Nuclear medicine program progress report for quarter ending December 31, 1992

    SciTech Connect

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Hasan, A.; Lambert, C.R.

    1993-03-01

    We describe the synthesis of the cis- and trans-iodovinyl isomers of the new ORNL cholinergic-muscarinicreceptorligand, 1 -azabicyclo[2.2-2]oct-3-yl[alpha]-hydroxy-[alpha]-(1-iodo-l-propen-3-yl)-[alpha]-phenylacetate ( IQNP''). This agent is prepared in high radiochemical yield, and the racemic mixture shows high specificity and selectivity for the cerebral and myocardial receptors. Since two chiral centers are present in this molecule, it is important to evaluate the importance of the absolute configuration of the two centers on receptor specificity. The tributyltin substrates were carefully separated by column chromatography, converted to the iodine-125 analogues by iododestannylation, and evaluated in rats in vivo. While the E'' (trans) isomer cleared rapidly from the receptor-rich areas of rat brain, the Z'' (cis) isomer showed high uptake in these areas but also high concentration in the cerebellum. In contrast, the E,Z-isomeric mixture showed good uptake and retention in the receptor rich areas. Also described in this report is a description of neutron flux measurements in the hydraulic tube position at the ORNL High Flux Isotope Reactor (HFIR). Also during this period, samples of [l-125]- and [l-131]-labeled racemic IQNP'' were supplied through a collaborative program with the Brookhaven National Laboratory for high resolution autoradiographic studies in rat tissues.

  14. Exxon catalytic coal-gasification process development program. Quarterly technical progress report, October-December 1979

    SciTech Connect

    Euker, Jr, C. A.

    1980-03-01

    Work continued on the catalyst recovery screening studies to evaluate the economic impacts of alternative processing approaches and solid-liquid separation techniques. Equipment specifications have been completed for two cases with countercurrent water washing using rotary-drum filters for the solid-liquid separations. Material and energy balances have been completed for an alternative methane recovery process configuration using low pressure stripping which requires 26% less horsepower than the Study Design system. A study has been initiated to identify trace components which might be present in the CCG gas loop and to assess their potential impacts on the CCG process. This information will be used to assist in planning an appropriate series of analyses for the PDU gasifier effluent. A study has been initiated to evaluate the use of a small conventional steam reformer operating in parallel with a preheat furnace for heat input to the catalytic gasifier which avoids the potential problem of carbon laydown. Preliminary replies from ten manufacturers are being evaluated as part of a study to determine the types and performance of coal crushing equipment appropriate for commercial CCG plants. A material and energy balance computer model for the CCG reactor system has been completed. The new model will provide accurate, consistent and cost-efficient material and energy balances for the extensive laboratory guidance and process definition studies planned under the current program. Other activities are described briefly.

  15. Nuclear medicine program progress report for quarter ending December 31, 1992

    SciTech Connect

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Hasan, A.; Lambert, C.R.

    1993-03-01

    We describe the synthesis of the cis- and trans-iodovinyl isomers of the new ORNL cholinergic-muscarinicreceptorligand, 1 -azabicyclo[2.2-2]oct-3-yl{alpha}-hydroxy-{alpha}-(1-iodo-l-propen-3-yl)-{alpha}-phenylacetate (``IQNP``). This agent is prepared in high radiochemical yield, and the racemic mixture shows high specificity and selectivity for the cerebral and myocardial receptors. Since two chiral centers are present in this molecule, it is important to evaluate the importance of the absolute configuration of the two centers on receptor specificity. The tributyltin substrates were carefully separated by column chromatography, converted to the iodine-125 analogues by iododestannylation, and evaluated in rats in vivo. While the ``E`` (trans) isomer cleared rapidly from the receptor-rich areas of rat brain, the ``Z`` (cis) isomer showed high uptake in these areas but also high concentration in the cerebellum. In contrast, the E,Z-isomeric mixture showed good uptake and retention in the receptor rich areas. Also described in this report is a description of neutron flux measurements in the hydraulic tube position at the ORNL High Flux Isotope Reactor (HFIR). Also during this period, samples of [l-125]- and [l-131]-labeled racemic ``IQNP`` were supplied through a collaborative program with the Brookhaven National Laboratory for high resolution autoradiographic studies in rat tissues.

  16. Nuclear medicine program progress report for quarter ending September 30, 1995

    SciTech Connect

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Luo, H.; McPherson, D.W.; Mirzadeh, S.

    1995-12-31

    In this report, we describe the results for study of the production of lutetium-177 ({sup 177}Lu) in the High Flux Isotope Reactor (HFIR). Two pathways for production of {sup 177}Lu were studied which involved both direct neutron capture on enriched {sup 176}Lu, {sup 176}Lu (n,{gamma}){sup 177}Lu, reaction and by decay of ytterbium-177 ({sup 177}Yb) produced by the {sup 176}Yb(n,{gamma}){sup 177}Yb ({beta}{sup {minus}} {sup {yields}}) reaction. Although the direct route is more straight forward and does not involve any separation steps, the indirect method via {beta}{sup {minus}}-decay of {sup 177}Yb has the advantage of providing carrier-free {sup 177}Lu, which would be required for antibody radiolabeling and other applications where very high specific activity is required.Substrates required for preparation of tissue-specific agents and several radioisotopes were also provided during this period through several Medical Cooperative Programs. These include the substrate for preparation of the ``BMIPP`` cardiac imaging which was developed in the ORNL Nuclear Medicine Program, which was provided to Dr. A. Giodamo, M.D. and colleagues at the Catholic University Hospital in Rome, Italy. Tungsten-188 produced in the ORNL HFIR was also provided to the Catholic University Hospital for fabrication of a tungsten-188/rhenium-188 generator to provide carrier-free rhenium-188 which will be used for preparation of rhenium-188 labeled methylenediphosphonate (MDP) for initial clinical evaluation for palliative treatment of bone pain (L. Troncone, M.D.). Samples of substrates for preparation of the new ORNL ``IQNP`` agent for imaging of muscarinic-cholinergic receptors were provided to the Karolinska Institute in Stockholm, Sweden, for preparation of radioiodinated IQNP for initial imaging studies with this new agent in monkeys and for tissue binding studies with human brain samples obtained from autopsy (C. Halldin, Ph.D.).

  17. 76 FR 48563 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-January Through March 2011...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-08

    ... considered reasonable and necessary in patients with mild cognitive impairment or early dementia only in the... Issuances notices are: June 28, 2010 (75 FR 36786), September 24, 2010 (75 FR 58790), December 17, 2010 (75 FR 79174), and March 31, 2011 (76 FR 17873). For the purposes of this quarterly notice, we...

  18. 76 FR 78267 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-July Through September 2011

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-16

    ... (CMS), HHS. ACTION: Notice. SUMMARY: This quarterly notice lists CMS manual instructions, substantive... of the addenda published in this notice. Addenda Contact Phone number I CMS Manual Instructions... Facilities. VIII American College of Cardiology- JoAnna Baldwin, MS (410) 786-7205 National...

  19. 76 FR 68467 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-April Through June 2011

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-04

    ... (CMS), HHS. ACTION: Notice. SUMMARY: This quarterly notice lists CMS manual instructions, substantive... each of the addenda published in this notice. Addenda Contact Phone number I CMS Manual Instructions... Sarah J. McClain. (410) 786-2294 Stent Facilities. VIII American College of JoAnna Baldwin, (410)...

  20. Northeast regional biomass program. First quarter report, October--December 1993

    SciTech Connect

    1994-05-01

    This progress report presents summaries of various projects which were in operation or being planned during this quarter period. Projects included testing the efficiency of using wood chips as fuel in heating systems, barriers to commercial development of wood pellet fuels, studies of more efficient and less polluting wood stoves, work on landfill gas utilization, directories of facilities using biomass fuels, surveys of biomass conversion processes to liquid fuels, for commercial development, etc.

  1. Fossil Energy Program quarterly progress report for the period ending June 30, 1984

    SciTech Connect

    McNeese, L.E.

    1984-09-01

    This quarterly report covers the progress made during the period April 1 through June 30 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, the Electric Power Research Institute, and by the Tennessee Valley Authority through inter-agency agreement with DOE.

  2. Fossil Energy Program. Quarterly progress report for the period ending March 31, 1984

    SciTech Connect

    McNeese, L.E.

    1984-06-01

    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, the Electric Power Research Institute, and by the Tennessee Valley Authority through inter-agency agreement with DOE.

  3. Fossil Energy Program quarterly progress report for the period ending September 30, 1984

    SciTech Connect

    McNeese, L.E.

    1984-12-01

    This quarterly report covers the progress made during the period July 1 through September 30 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, the Electric Power Research Institute, and by the Tennessee Valley Authority through inter-agency agreement with DOE.

  4. U. S. fast reactor materials and structures program

    SciTech Connect

    Harms, W.O.; Purdy, C.M.

    1984-01-01

    The U.S. DOE has sponsored a vigorous breeder reactor materials and structures program for 15 years. Important contributions have resulted from this effort in the areas of design (inelastic rules, verified methods, seismic criteria, mechanical properties data); resolution of licensing issues (technical witnessing, confirmatory testing); construction (fabrication/welding procedures, nondestructive testing techniques); and operation (sodium purification, instrumentation and chemical analysis, radioactivity control, and in-service inspection. The national LMFBR program currently is being restructured. The Materials and Structures Program will focus its efforts in the following areas: (1) removal of anticipated licensing impediments through confirmation of the adequacy of structural design methods and criteria for components containing welds and geometric discontinuities, the generation of mechanical properties for stainless steel castings and weldments, and the evaluation of irradiation effects; (2) qualification of modified 9 Cr-1 Mo steel and tribological coatings for design flexibility; (3) development of improved inelastic design guidelines and procedures; (4) reform of design codes and standards and engineering practices, leading to simpler, less conservative rules and to simplified design analysis methods; and (5) incorporation of information from foreign program.

  5. Atmospheric Radiation Measurement Program Climate Research Facility Operation quarterly report July 1 - September 30, 2010.

    SciTech Connect

    Sisterson, D. L.

    2010-10-26

    Individual raw datastreams from instrumentation at the Atmospheric Radiation Measurement (ARM) Climate Research Facility 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 ARM 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 datastream, 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 FY2010 for the Southern Great Plains (SGP) site is 2097.60 hours (0.95 2208 hours this quarter). The OPSMAX for the North Slope of Alaska (NSA) locale is 1987.20 hours (0.90 2208) and for the Tropical Western Pacific (TWP) locale is 1876.80 hours (0.85 2208). The first ARM Mobile Facility (AMF1) deployment in Graciosa Island, the Azores, Portugal, continues, so the OPSMAX time this quarter is 2097.60 hours (0.95 x 2208). 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 datastream. Data availability reported here refers to the average of the individual, continuous datastreams 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

  6. Energy Programs at the Johns Hopkins University Applied Physics Laboratory, Quarterly Report, January-March 1981

    SciTech Connect

    1981-03-01

    The Johns Hopkins University Applied 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 March 1981. The Energy Quarterly Report is divided into three sections. The first, Geothermal Energy Development Planning and Technical Assistance, supported by the Department of Energy/Division of Geothermal Energy (DOE/DGE), contains reports on the progress of geothermal-related tasks on which effort was concentrated during the quarter. The second section, Siting of Critical Facilities, supported by the Nuclear Regulatory Commission (NRC) and in-house funds, contains reports on geologic investigations in western Connecticut and areas in adjacent New York, development of seismotectonic domains, and fracture permeability in siting hazardous waste repositories. The third section, Energy Conservation and Storage Techniques, supported by the Argonne National Laboratory (ANL), reports on institutional barriers to landfill methane recovery and the need for state legislation.

  7. Energy Programs at the Johns Hopkins University Applied Physics Laboratory, Quarterly Report, April-June 1980

    SciTech Connect

    1980-06-01

    The Johns Hopkins University Applied Physics Laboratory, under contracts with several agencies of the federal government and an agency of the State of Maryland, is engaged in developing energy resources, utilization concepts, and monitoring and storage methods. This Quarterly Report summarizes the work on the various tasks as of 30 June 1980. The Energy Quarterly Report is divided into three sections. The first, Geothermal Energy Development Planning and Technical Assistance, supported by the Department of Energy/Division of Geothermal Energy (DOE/DGE), contains reports on the progress of geothermal-related tasks on which effort was concentrated during the quarter. The second section, Operational Research, Hydroelectric Power Development, supported by the Department of Energy/Resource Applications (DOE/RA), contains reports on small-scale hydroelectric investigations in the southeastern states. The third section, Energy Conversion and Storage Techniques, contains three articles. The first is on data analysis of OTEC core unit condenser tests, and is supported by the Department of Energy/Division of Central Solar Technology (DOE/CST). The second is on the current status of the Community Annual Storage Energy System at the U.S. Naval Air Station, Norfolk, Va., and is supported by the Department of Energy and the Department of Defense, Naval Facilities Engineering Command/Atlantic Division. The third is on utilization of landfill methane and is supported by Argonne National Laboratory.

  8. (COMEDIE program review and fission product transport in MHTGR reactor)

    SciTech Connect

    Stansfield, O.M.

    1990-03-15

    The subcontract between Martin Marietta Energy Systems, Inc., and the CEA provides for the refurbishment of the high pressure COMEDIE test loop in the SILOE reactor and a series of experiments to characterize fission product lift-off from MHTGR heat exchanger surfaces under several depressurization accident scenarios. The data will contribute to the validation of models and codes used to predict fission product transport in the MHTGR. In the meeting at CEA headquarters in Paris the program schedule and preparation for the DCAA and Quality Assurance audits were discussed. Long-range interest in expanded participation in the gas-cooled reactor technology Umbrella Agreement was also expressed by the CEA. At the CENG, in Grenoble, technical details on the loop design, fabrication components, development of test procedures, and preparation for the DOE quality assurance (QA) audit in May were discussed. After significant delays in CY 1989 it appears that good progress is being made in CY 1990 and the first major test will be initiated by December. An extensive list of agreements and commitments was generated to facilitate the coordination and planning of future work. 2 figs., 2 tabs.

  9. Fossil Energy Program. Quarterly progress report for the period ending December 31, 1984. [Ni-Fe aluminides

    SciTech Connect

    McNeese, L.E.

    1985-03-01

    This quarterly report covers the progress made during the period October 1 through December 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, the Electric Power Research Institute, and by the Tennessee Valley Authority through inter-agency agreement with DOE. Summaries and progress reports are presented for the following tasks: (1) materials research and development; (2) fossil energy environmental programs; (3) coal conversion development; (4) process analysis and engineering evaluations; (5) generalized equilibrium models of liquid and gaseous fuels supply; (6) fluidized bed combustion joint program; and (7) coal chemistry.

  10. A FAST BREEDER REACTOR SPENT FUEL MEASUREMENTS PROGRAM FOR BN-350 REACTOR

    SciTech Connect

    P. STAPLES; J. HALBIG; ET AL

    1999-04-01

    A project to verify the fissile content of fast breeder reactor spent nuclear fuel is underway in the Republic of Kasakhstan. There are a variety of assembly types with different irradiation histories and profiles in the reactor that require a variety of measurement and analysis procedures. These procedures will be discussed and compared as will the general process that has been designed to resolve any potential measurement discrepancies. The underwater counter is part of a system that is designed to assist the International Atomic Energy Agency (IAEA) in maintaining continuity of knowledge from the time of measurement until the measured item is placed in a welded container with a unique identification. In addition to satisfying IAEA requirements for the spent nuclear fuel, this measurement program is able to satisfy some of the measurement requirements for the Kasakhstan Atomic Energy Agency concerning the repackaging of the spent nuclear fuel into a standard canister. The project is currently operational in a mode requiring the IAEA's continuous presence.

  11. Feasibility Study of Supercritical Light Water Cooled Reactors for Electric Power Production, Progress Report for Work Through September 2003, 2nd Annual/8th Quarterly Report

    SciTech Connect

    Philip E. MacDonald

    2003-09-01

    The supercritical water-cooled reactor (SCWR) is one of the six reactor technologies selected for research and development under the Generation-IV program. SCWRs are promising advanced nuclear systems because of their high thermal efficiency (i.e., about 45% vs. about 33% efficiency for current Light Water Reactors, LWRs) and considerable plant simplification. SCWRs are basically LWRs operating at higher pressure and temperatures with a direct once-through cycle. Operation above the critical pressure eliminates coolant boiling, so the coolant remains single-phase throughout the system. Thus the need for recirculation and jet pumps, a pressurizer, steam generators, steam separators and dryers is eliminated. The main mission of the SCWR is generation of low-cost electricity. It is built upon two proven technologies, LWRs, which are the most commonly deployed power generating reactors in the world, and supercritical fossil-fired boilers, a large number of which is also in use around the world.

  12. Feasibility Study of Supercritical Light Water Cooled Fast Reactors for Actinide Burning and Electric Power Production, 3rd Quarterly Report

    SciTech Connect

    Mac Donald, Philip Elsworth

    2002-06-01

    The use of light water at supercritical pressures as the coolant in a nuclear reactor offers the potential for considerable plant simplification and consequent capital and O&M cost reduction compared with current light water reactor (LWR) designs. Also, given the thermodynamic conditions of the coolant at the core outlet (i.e. temperature and pressure beyond the water critical point), very high thermal efficiencies of the power conversion cycle are possible (i.e. up to about 45%). Because no change of phase occurs in the core, the need for steam separators and dryers as well as for BWR-type re-circulation pumps is eliminated, which, for a given reactor power, results in a substantially shorter reactor vessel and smaller containment building than the current BWRs. Furthermore, in a direct cycle the steam generators are not needed.

  13. Advanced Light Water Reactor Program: Program management and staff review methodology

    SciTech Connect

    Moran, D.H.

    1986-12-01

    This report summarizes the NRC/EPRI coordinated effort to develop design requirements for a standardized advanced light water reactor (ALWR) and the procedures for screening and applying new generic safety issues to this program. The end-product will be an NRC-approved ALWR Requirements Document for use by the nuclear industry in generating designs of LWRs to be constructed for operation in the 1990s and beyond.

  14. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report July 1 - September 30, 2005

    SciTech Connect

    DL Sisterson

    2005-09-30

    Description. Individual raw data streams from instrumentation at the ACRF fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at 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 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 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 Alaska (NSA) site is 1,987.2 hours (0.90 × 2,208), and that for the Tropical Western Pacific (TWP) site 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 of data in the Archive represents the average percent of the time (24 hours per day, 92 days for this quarter) the instruments were operating

  15. Fossil-energy program. Quarterly progress report for June 30, 1983

    SciTech Connect

    McNeese, L.E.

    1983-08-01

    This quarterly report covers the progress made during the period March 31 through June 30 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 agreement with DOE.

  16. Fossil-Energy-Program. Quarterly progress report for period ending December 31, 1982

    SciTech Connect

    McNeese, L.E.

    1983-03-01

    This quarterly report covers the progress made during the period October 1 through December 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 agreement with the DOE.

  17. Fossil Energy Program. Quarterly progress report for the period ending September 30, 1983

    SciTech Connect

    Not Available

    1983-11-01

    This quarterly report covers the progress made during the period July 1 through September 30 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, Offices 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 agreement with DOE.

  18. Fossil Energy Program quarterly progress report for the period ending December 31, 1983

    SciTech Connect

    McNeese, L.E.

    1984-03-01

    This quarterly report covers the progress made during the period October 1 through December 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 agreement with DOE.

  19. Fossil-energy program. Quarterly progress report for the period ending September 30, 1982

    SciTech Connect

    McNeese, L.E.

    1982-12-01

    This quarterly report covers the progress made during the period July 1 through September 30 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 with the DOE.

  20. Unocal Parachute Creek Shale Oil Program Environmental Monitoring Program. Quarterly report, Fourth Quarter, 1990. Rept. for 1 Sep 90-31 Dec 90

    SciTech Connect

    Not Available

    1991-02-28

    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 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 socioeconomic impacts during the period 1986-1993. Phase I of the project is to produce 10,000 barrels per day of syncrude from oil shale, using the Unishale B process. Ten pages of text describe ten compliance reports, supplemental sampling at eight sites, and industrial hygiene monitoring results. The remaining pages contain detailed data sheets for ambient air and meteorological monitoring.

  1. US Department of Energy 1992--1993 Reactor Sharing Program. Final report

    SciTech Connect

    Vernetson, W.G.

    1994-04-01

    The University of Florida Training Reactor serves as a host institution to support various educational institutions which are located primarily within the state of Florida. All users and uses were carefully screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program. Three tables are included that provide basic information about the 1992--1993 program and utilization of the reactor facilities by user institutions.

  2. 10 CFR Appendix H to Part 50 - Reactor Vessel Material Surveillance Program Requirements

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Reactor Vessel Material Surveillance Program Requirements H Appendix H to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. H Appendix H to Part 50—Reactor Vessel Material Surveillance Program Requirements I. Introduction II....

  3. 10 CFR Appendix H to Part 50 - Reactor Vessel Material Surveillance Program Requirements

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Reactor Vessel Material Surveillance Program Requirements H Appendix H to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. H Appendix H to Part 50—Reactor Vessel Material Surveillance Program Requirements I. Introduction II....

  4. 10 CFR Appendix H to Part 50 - Reactor Vessel Material Surveillance Program Requirements

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Reactor Vessel Material Surveillance Program Requirements H Appendix H to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. H Appendix H to Part 50—Reactor Vessel Material Surveillance Program Requirements I. Introduction II....

  5. 10 CFR Appendix H to Part 50 - Reactor Vessel Material Surveillance Program Requirements

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Reactor Vessel Material Surveillance Program Requirements H Appendix H to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. H Appendix H to Part 50—Reactor Vessel Material Surveillance Program Requirements I. Introduction II....

  6. 10 CFR Appendix H to Part 50 - Reactor Vessel Material Surveillance Program Requirements

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Reactor Vessel Material Surveillance Program Requirements H Appendix H to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. H Appendix H to Part 50—Reactor Vessel Material Surveillance Program Requirements I. Introduction II....

  7. Federal assistance program. Quarterly project progress report, January 1998--March 1998

    SciTech Connect

    1998-04-01

    This report summarizes geothermal technical assistance, R&D and technology transfer activities of the Geo-Heat Center at Oregon Institute of Technology for the second quarter of FY-98-98 (January-March, 1998). It describes 268 contacts with parties during this period related to technical assistance with geothermal direct heat projects. Areas dealt with include requests for general information including maps and material for high school debates, and material on geothermal heat pumps, resource and well data, spacing heating and cooling, greenhouses, aquaculture, equipment, district heating, resorts and spas, industrial applications, electric power and snow melting. Research activities include work on model construction specifications for line shaft submersible pumps and plate heat exchangers and a comprehensive aquaculture developer package. The revised Geothermal Direct Use Engineering and Design Guidebooks was completed, published and is available for distribution. Outreach activities include the publication of the Quarterly Bulletin (Vol. 19, No. 1) which was devoted entirely to geothermal equipment, dissemination of information mainly through mailings of publications, tours of local geothermal uses, geothermal library acquisitions and use, participation in workshops, short courses and technical meetings by the staff, and progress monitor reports on geothermal activities.

  8. Status of reduced enrichment programs for research reactors in Japan

    SciTech Connect

    Kanda, Keiji; Nishihara, Hedeaki; Shirai, Eiji; Oyamada, Rokuro; Sanokawa, Konomo

    1997-08-01

    The reduced enrichment programs for the JRR-2, JRR-3, JRR-4 and JMTR of Japan Atomic Energy Research Institute (JAERI), and the KUR of Kyoto University Research Reactor Institute (KURRI) have been partially completed and are mostly still in progress under the Joint Study Programs with Argonne National Laboratory (ANL). The JMTR and JRR-2 have been already converted to use MEU aluminide fuels in 1986 and 1987, respectively. The operation of the upgraded JRR-3(JRR-3M) has started in March 1990 with the LEU aluminide fuels. Since May 1992, the two elements have been inserted in the KUR. The safety review application for the full core conversion to use LEU silicide in the JMTR was approved in February 1992 and the conversion has been done in January 1994. The Japanese Government approved a cancellation of the KUHFR Project in February 1991, and in April 1994 the U.S. Government gave an approval to utilize HEU in the KUR instead of the KUHFR. Therefore, the KUR will be operated with HEU fuel until 2001. Since March 1994, Kyoto University is continuing negotiation with UKAEA Dounreay on spent fuel reprocessing and blending down of recovered uranium, in addition to that with USDOE.

  9. Reactor Materials Program: Mechanical properties of irradiated Types 304 and 304L stainless steel weldment components

    SciTech Connect

    Sindelar, R.L.; Caskey, G.R. Jr.

    1991-12-01

    The vessels (reactor tanks) of the Savannah River Site nuclear production reactors constructed in the 1950's are comprised of Type 304 stainless steel with Type 308 stainless steel weld filler. Irradiation exposure to the reactor tank sidewalls through reactor operation has caused a change in the mechanical properties of these materials. A database of as-irradiated mechanical properties for site-specific materials and irradiation conditions has been produced for reactor tank structural analyses and to quantify the effects of radiation-induced materials degradation for evaluating reactor service life. The data has been collected from the SRL Reactor Materials Program (RMP) irradiations and testing of archival stainless steel weldment components and from previous SRL programs to measure properties of irradiated reactor Thermal Shield weldments and reactor tank (R-tank) sidewall material. Irradiation programs of the RMP are designed to quantify mechanical properties at tank operating temperatures following irradiation to present and future tank wall maximum exposure conditions. The exposure conditions are characterized in terms of fast neutron fluence (E{sub n} > 0.1 MeV) and displacements per atom (dpa){sup 3}. Tensile properties, Charpy-V notch toughness, and elastic-plastic fracture toughness were measured for base, weld, and weld heat-affected zone (HAZ) weldment components from archival piping specimens following a Screening Irradiation in the University of Buffalo Reactor (UBR) and following a Full-Term Irradiation in the High Flux Isotope Reactor (HFIR).

  10. Reactor Materials Program: Mechanical properties of irradiated Types 304 and 304L stainless steel weldment components

    SciTech Connect

    Sindelar, R.L.; Caskey, G.R. Jr.

    1991-12-01

    The vessels (reactor tanks) of the Savannah River Site nuclear production reactors constructed in the 1950`s are comprised of Type 304 stainless steel with Type 308 stainless steel weld filler. Irradiation exposure to the reactor tank sidewalls through reactor operation has caused a change in the mechanical properties of these materials. A database of as-irradiated mechanical properties for site-specific materials and irradiation conditions has been produced for reactor tank structural analyses and to quantify the effects of radiation-induced materials degradation for evaluating reactor service life. The data has been collected from the SRL Reactor Materials Program (RMP) irradiations and testing of archival stainless steel weldment components and from previous SRL programs to measure properties of irradiated reactor Thermal Shield weldments and reactor tank (R-tank) sidewall material. Irradiation programs of the RMP are designed to quantify mechanical properties at tank operating temperatures following irradiation to present and future tank wall maximum exposure conditions. The exposure conditions are characterized in terms of fast neutron fluence (E{sub n} > 0.1 MeV) and displacements per atom (dpa){sup 3}. Tensile properties, Charpy-V notch toughness, and elastic-plastic fracture toughness were measured for base, weld, and weld heat-affected zone (HAZ) weldment components from archival piping specimens following a Screening Irradiation in the University of Buffalo Reactor (UBR) and following a Full-Term Irradiation in the High Flux Isotope Reactor (HFIR).

  11. Oklo: natural fission reactor program. Progress report, July 1-September 30, 1979

    SciTech Connect

    Norris, A.E.

    1980-01-01

    Nearly 200 samples were collected at the Oklo mine in Gabon this quarter for shipment to the United States to continue studies of lead, ruthenium, and technetium migration around natural fission reactors. The first analyses of samples collected near a rich uranium ore body in Canada show the presence of radiogenic lead in pyrite and sandstone materials. Analyses of additional samples are underway to permit the interpretation of the data in terms of transport paths. A technique was developed this quarter to eliminate the interference of organic materials during the mass spectrometric analyses of ruthenium in Oklo samples with high asphaltic contents. A proposal was drafted for a study of naturally occurring radionuclide migration at rich uranium ore bodies in Australia to be performed jointly by the US Department of Energy and the Australian Atomic Energy Commission.

  12. Light Water Reactor Sustainability Program. Digital Architecture Requirements

    SciTech Connect

    Thomas, Kenneth; Oxstrand, Johanna

    2015-03-01

    The Digital Architecture effort is a part of the Department of Energy (DOE) sponsored Light-Water Reactor Sustainability (LWRS) Program conducted at Idaho National Laboratory (INL). The LWRS program is performed in close collaboration with industry research and development (R&D) programs that provides the technical foundations for licensing and managing the long-term, safe, and economical operation of current nuclear power plants (NPPs). One of the primary missions of the LWRS program is to help the U.S. nuclear industry adopt new technologies and engineering solutions that facilitate the continued safe operation of the plants and extension of the current operating licenses. Therefore, a major objective of the LWRS program is the development of a seamless digital environment for plant operations and support by integrating information from plant systems with plant processes for nuclear workers through an array of interconnected technologies. In order to get the most benefits of the advanced technology suggested by the different research activities in the LWRS program, the nuclear utilities need a digital architecture in place to support the technology. A digital architecture can be defined as a collection of information technology (IT) capabilities needed to support and integrate a wide-spectrum of real-time digital capabilities for nuclear power plant performance improvements. It is not hard to imagine that many processes within the plant can be largely improved from both a system and human performance perspective by utilizing a plant wide (or near plant wide) wireless network. For example, a plant wide wireless network allows for real time plant status information to easily be accessed in the control room, field workers’ computer-based procedures can be updated based on the real time plant status, and status on ongoing procedures can be incorporated into smart schedules in the outage command center to allow for more accurate planning of critical tasks. The goal

  13. Kansas State University DOE/KEURP Site Operator Program. Year 2, Second quarter report, October 1--December 31, 1992

    SciTech Connect

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

    1992-12-31

    This concludes the sixth quarter that Kansas State University has been under contract to the US Department of Energy and the Kansas Electric Utility Research Program to demonstrate electric vehicle technology. The G-Van continues to perform within acceptable limits, although the batteries and the charger have caused some problems. Dave Harris, Chloride, has been working with K-State to correct these problems. It may very well be that the limited mileage (less than 25 miles) can be increased by extending the charge cycle (overcharging) the batteries. Soleq Corp. has failed to deliver contracted vehicles. A dual shaft electric propulsion minivan, built by Eaton Corp. in 1987, will be shipped here. On the infrastructure side, EHV Corp. is developing curbside and home charging stations.

  14. Advanced Two-Phase Flow Instrumentation Program. Quarterly progress report, April-June 1980

    SciTech Connect

    Turnage, K.G.; Davis, C.E.; Anderson, R.L.; Miller, G.N.

    1980-12-01

    Work performed to develop and evaluate liquid level sensors for in-vessel use in pressurized water reactors is described. Experiments were performed with three thermal-type level sensors in natural convection to saturated water and steam. Pressures in those tests ranged from 0.1 to 8.6 MPa (15 to 1250 psia). Thermal-type sensors were also tested in steam-water forced convection at low and moderate pressures. Sensor response was found to be insensitive to flow velocity and void fraction but sensitive to the presence or absence of a liquid phase. A series of meetings was held with representatives of three pressurized water reactor vendors regarding research goals and implementation of reactor-vessel monitoring instrumentation.

  15. Characterization of porosity via secondary reactor. Quarterly technical progress report, 1 October 1992--31 December 1992

    SciTech Connect

    Calo, J.M.

    1992-12-31

    In this quarterly technical Progress report, we summarize the progress which has been achieved with the development of the small angle scattering capability to be used in the current project. In particular, the following was accomplished during the reporting period. The parameter estimation code, MARQFIT, has been tested and is fully operational. The code has been applied to small angle neutron scattering (SANS) data on coals swollen with deuterated solvents. Application of the FPPS model to these data indicated that the large sphere distribution apparently requires a mean greater than 1000{Angstrom}. This was attributed to the influence of interparticle voids. Specific surface areas were also estimated for these coals. Application of this model to the coal chars used in the current project will not be subject to the same effects.

  16. The Ohio State University Reactor Sharing Program [August 15, 2000 - May 31, 2001

    SciTech Connect

    Myser, Richard D.

    2002-01-04

    During the period from August 15, 2000 through may 31, 2001 the Ohio State University (OSU) Research Reactor participated in the Reactor Sharing Program by providing services to nine colleges and universities and four secondary school organizations. A total of about 17 faculty and 170 students utilized their facilities. The staff of the OSU Research Reactor is generally involved in four types of experiments at the Nuclear Reactor Laboratory. Included are introductions to nuclear research, neutron activation analysis, material irradiation, and classes that measure various reactor parameters.

  17. Quarterly technical progress report, October-December 1982 on Energy Conversion Research and Development Programs

    SciTech Connect

    Not Available

    1983-10-01

    In this quarterly technical progress report, UTSI reports on the continued design work for the low mass flow train superheater. The detailed design of this component continued and the overall arrangement drawing for the superheater and air heater was finalized. The air heater procurement reached the point of contract award, but the actual purchase order award was held up pending receipt of additional funding from the Department of Energy. Testing activity reported includes two additional tests in the LMF1C series, which concludes this test series. Test data are presented, along with preliminary analyses for the combustor, nozzle, diagnostic channel, diffuser, radiant furnace/secondary combustor and Materials Test Module. In addition to the nitrogen oxide test measurements, corrosion and erosion rates for the boiler tube specimens and the materials test module are reported.

  18. High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, January 1-March 31, 1980

    SciTech Connect

    Ball, S.J.; Cleveland, J.C.; Conklin, J.C.; Harrington, R.M.

    1980-08-01

    Work continued on development of the ORTAP, ORECA, and BLAST codes; and verification studies were continued on the ORECA, CORTAP, and BLAST codes. An improved steam turbine plant model (ORTURB) for use in ORTAP was developed and checked. Predictions from BLAST, CORTAP, and ORECA were compared with various transient test data from the Fort St. Vrain reactor.

  19. 78 FR 45233 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-April Through June 2013

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-26

    ... Listing of Program Issuances--April Through June 2013 AGENCY: Centers for Medicare & Medicaid Services... through June 2013, relating to the Medicare and Medicaid programs and other programs administered by...

  20. 77 FR 49799 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-April Through June 2012

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-17

    ... Listing of Program Issuances--April Through June 2012 AGENCY: Centers for Medicare & Medicaid Services... through June 2012, relating to the Medicare and Medicaid programs and other programs administered by...

  1. Design reliability assurance program for Korean next generation reactor

    SciTech Connect

    Lee, Beom-Su; Han, Jin-Kyu; Na, Jang Hwan; Yoo, Kyung Yeong

    1997-12-01

    The Korean Next Generation Reactor (KNGR) project is to develop standardized nuclear power plant design for the construction of future nuclear power plants in Korea. The main purpose of the KNGR project is to develop the advanced nuclear power plants, which enhance safety and economics significantly through the incorporation of design concepts for severe accident prevention and mitigation, supplementary passive safety concept, simplification and application of modularization and so on. For those, Probabilistic Safety Assessment (PSA) and availability study will be performed at the early stage of the design, and the Design Reliability Assurance Program (D-RAP) is applied in the development of the KNGR to ensure that the safety and availability evaluated in the PSA and availability study at the early phase of the design is maintained through the detailed design, construction, procurement and operation of the plants. This paper presents the D-RAP concept that could be applied at the stage of the basic design of the nuclear power plants, based on the models for the reference plants and/or similar plants. 4 refs., 1 fig.

  2. Oklo-natural fission reactor program. Progress report, October 1, 1979-December 31, 1979

    SciTech Connect

    Norris, A.E.

    1980-03-01

    The study of lead, ruthenium, and technetium transport in nature requires the mass spectrometric analyses of large numbers of geologic samples. This quarter about 200 samples arrived from Gabon, which were collected at the Oklo mine in September. Work was performed to improve the lead and ruthenium chemical procedures and the mass spectrometric instrumentation in preparation for analyzing many of the Oklo samples and a large number of the 402 samples on hand from Key Lake, Canada. Data concerning ruthenium isotopic alterations from samples near an Oklo natural fission reactor zone indicated that ruthenium or technetium were not transported to distances greater than the 10 meters detected previously.

  3. RETRAC: A program for the analysis of materials test reactors

    SciTech Connect

    Baggoura, B.; Hamidouche, T.; Bousbia-Salah, A. . Lab. des Analyses de Surete)

    1994-09-01

    REactor TRansient Analysis Code (RETRAC) is a computer code specially developed for the analysis of materials test reactor (MTR) cores. The RETRAC code uses a set of coupled neutron point-kinetics equations and thermal-hydraulic conservation laws to simulate nuclear reactor core behavior under transient or accident conditions. The reactor core is represented by a single equivalent unit cell composed of three regions: fuel, clad, and moderator (coolant). Validation tests of the RETRAC code were performed by using the International Atomic Energy Agency 10-MW benchmark cores, for protected transients. Further assessment studies are in progress using experimental data. The code was developed on a VAX-4000 working station.

  4. A Study of the Acceptance to Graduate Schools of Students with a Planned Program of Sixty-Six Quarter Hours of Pass-Fail Credit.

    ERIC Educational Resources Information Center

    Oberlin, Lynn

    The professional portion of the elementary and early childhood teacher education program at the University of Florida (UF) is taken on a pass-fail basis. A student completing this program has 66 quarter hours of pass-fail credit and a letter written by a faculty member who has worked with her or him for two years. The purpose of this study was to…

  5. Reactor Materials Program probability of indirectly--induced failure of L and P reactor process water piping

    SciTech Connect

    Daugherty, W.L.

    1988-03-11

    The design basis accident for the Savannah River Production Reactors is the abrupt double-ended guillotine break (DEGB) of a large process water pipe. This accident is not considered credible in light of the low applied stresses and the inherent ductility of the piping material. The Reactor Materials Program was initiated to provide the technical basis for an alternate credible design basis accident. One aspect of this work is to determine the probability of the DEGB; to show that in addition to being incredible, it is also highly improbable. The probability of a DEGB is broken into two parts: failure by direct means, and indirectly-induced failure. Failure of the piping by direct means can only be postulated to occur if an undetected crack grows to the point of instability, causing a large pipe break. While this accident is not as severe as a DEGB, it provides a conservative upper bound on the probability of a direct DEGB of the piping. The second part of this evaluation calculates the probability of piping failure by indirect causes. Indirect failure of the piping can be triggered by an earthquake which causes other reactor components or the reactor building to fall on the piping or pull it from its supports. Since indirectly-induced failure of the piping will not always produce consequences as severe as a DEGB, this gives a conservative estimate of the probability of an indirectly- induced DEGB. This second part, indirectly-induced pipe failure, is the subject of this report. Failure by seismic loads in the piping itself will be covered in a separate report on failure by direct causes. This report provides a detailed evaluation of L reactor. A walkdown of P reactor and an analysis of the P reactor building provide the basis for extending the L reactor results to P reactor.

  6. Fischer-Tropsch synthesis in slurry-reactor systems. Quarterly report, November 1, 1981 to January 31, 1982

    SciTech Connect

    Satterfield, C.N.; Bartos, T.; Huff, G.A. Jr.; Stenger, H.

    1982-01-01

    A detailed study of mass transfer effects with a reduced fused magnetite catalyst has now been completed and is summarized in an appended paper, Mass Transfer and Product Selectivity in a Mechanically-Stirred Fischer-Tropsch Slurry Reactor, by Charles N. Satterfield and George A. Huff, Jr. Analysis of our heavier hydrocarbon products indicates that they yield a value of ..cap alpha.. = 0.93 on a Flory plot, considerably higher than the values of ..cap alpha.. of about 0.7 found with lighter products. Iron catalysts may exhibit two kinds of sites with considerably different kinetic behavior. At the request of Drs. Sapienza and Sleigeir of the Brookhaven National Laboratory, we ran a sample of their SOSS catalyst in our reactor facility at 100 psig. Activity was low, but this may have been because this particular catalyst is possibly better suited for higher pressures.

  7. Particulate behavior in a controlled-profile pulverized coal-fired reactor: A study of coupled turbulent particle dispersion and thermal radiation transport. Quarterly technical progress report, December 15, 1992--March 14, 1993

    SciTech Connect

    Queiroz, M.; Webb, B.W.

    1993-05-01

    During the sixth quarter progress has been made in the following areas: Preparation for reactor refurbishment, instrumentation development, coal acquisition for experimental tests, and radiation and particle dispersion modelling. Refurbishment of the Controlled Profile Reactor was initiated this summer and is completed. Construction work for the local transmissometer probe is also now completed. This laser-based instrument, combined with the data from the PCSV probe will enable estimate of the local concentration of particulates below 0.5 {mu}m in size. Additionally, it will permit measurement of the temporal statistics of the local particulate number density.

  8. Participation in the U.S. Department of Energy Reactor Sharing Program. Progress report

    SciTech Connect

    Mulder, R.U.; Benneche, P.E.; Hosticka, B.

    1997-03-01

    The objective of the DOE supported Reactor Sharing Program is to increase the availability of university nuclear reactor facilities to non-reactor-owning educational institutions. The educational and research programs of these user institutions is enhanced by the use of the nuclear facilities. Several methods have been used by the UVA Reactor Facility to achieve this objective. First, many college and secondary school groups toured the Reactor Facility and viewed the UVAR reactor and associated experimental facilities. Second, advanced undergraduate and graduate classes from area colleges and universities visited the facility to perform experiments in nuclear engineering and physics which would not be possible at the user institution. Third, irradiation and analysis services at the Facility have been made available for research by faculty and students from user institutions. Fourth, some institutions have received activated material from UVA for use at their institutions. These areas are discussed here.

  9. High temperature ceramic membrane reactors for coal liquid upgrading. Quarterly report No. 1, September 21, 1989--December 20, 1989

    SciTech Connect

    Tsotsis, T.T.

    1992-06-19

    In this project we well evaluate the performance of Sel-Gel alumina membranes in coal liquid upgrading processes under realistic temperature and pressure conditions and investigate the feasibility of using such membranes in a membrane reactor based coal liquid upgrading process. In addition, the development of novel ceramic membranes with enhanced catalytic activity for coal-liquid upgrading applications, such as carbon-coated alumina membranes, will be also investigated. (VC)

  10. Combined sift and methanation in a fluidized-bed reactor. Quarterly progress report, 1 July 1980-30 September 1980

    SciTech Connect

    Streeter, R.C.

    1980-10-01

    Four bench-scale reactor tests were completed. One test employed the older life-test apparatus to evaluate two samples of a Ru/Ni-on-titania catalyst from Johnson Matthey. The remaining three bench-scale tests were conducted using the newer bench-scale reactor with feed gas H/sub 2//CO ratios of 2/1 and 1/1. The tests at H/sub 2//CO = 2/1 (no steam) completed a series designed to show the effect of temperature on carbon formation potential. The results were inconclusive, however, due to one temperature upset and occasional plugging of the reactor tubes with carbon deposits. Nevertheless, the data did indicate that the catalysts were able to remain active for longer periods of time at the higher temperatures despite significant carbon buildup. The bench-scale test at H/sub 2//CO = 1/1 was carried out at 950/sup 0/F in the absence of steam. Not surprisingly, therefore, significant carbon deposition was again experienced. This series of tests will be continued to examine the effect of increasing steam concentrations on carbon formation potential. A 5-day PEDU test (Test SM-4) was conducted using the UCI catalyst. The catalyst showed very high activity in steady-state periods of 36 hours at H/sub 2//CO = 1/1 (without steam) and 39 hours at H/sub 2//CO = 1/1 (with a steam/gas ratio of 0.2). Most importantly, the carbon content of the catalyst did not increase throughout the course of the test. The only drawback was that the catalyst tended to compact in a hard layer on the inner walls of the distributor, interfering with temperature control near the reactor inlet.

  11. Library Service Enhancement Program. First Quarterly Progress Report to the Council on Library Resources.

    ERIC Educational Resources Information Center

    Harrison, Orion

    This progress report of the Georgia Southern College Library presents information on a comprehensive program that involved the library in all aspects of the academic program. Objectives were to: (1) inform the college community about present and planned library services and programs; (2) attempt to expose all undergraduates to the organization of…

  12. High temperature ceramic membrane reactors for coal liquid upgrading. Quarter report No. 9, September 21, 1991--December 20, 1991

    SciTech Connect

    Tsotsis, T.T.

    1992-07-01

    In this project we intend to study a novel process concept, i.e, the use of ceramic membranes reactors in upgrading of coal derived liquids. Membrane reactors have been used in a number of catalytic reaction processes in order to overcome the limitations on conversion imposed by thermodynamic equilibrium. They have, furthermore, the inherent capability for combining reaction and separation in a single step. Thus they offer promise for improving and optimizing yield, selectivity and performance of processes involving complex liquids, as those typically found in coal liquid upgrading. Ceramic membranes are a new class of materials, which have shown promise in a variety of industrial applications. Their mechanical and chemical stability coupled with a wide range of operating temperatures and pressures make them suitable for environments found in coal liquid upgrading. In this project we will evaluate the performance of Sol-Gel alumina membranes in coal liquid upgrading processes under realistic temperature and pressure conditions and investigate the feasibility of using such membranes in a membrane reactor based coal liquid upgrading process. In addition, the development of novel ceramic membranes with enhanced catalytic activity for coal-liquid upgrading applications, such as carbon-coated alumina membranes, will be also investigated.

  13. High temperature ceramic membrane reactors for coal liquid upgrading. Quarterly report No. 12, June 21, 1992--September 20, 1992

    SciTech Connect

    Tsotsis, T.T.

    1992-12-31

    In this project we intend to study a novel process concept, i.e.,the use of ceramic membranes reactors in upgrading of coal derived liquids. Membrane reactors have been used in a number of catalytic reaction processes in order to overcome the limitations on conversion imposed by thermodynamic equilibrium. They have, furthermore, the inherent capability for combining reaction and separation in a single step. Thus they offer promise for improving and optimizing yield, selectivity and performance of processes involving complex liquids, as those typically found in coal liquid upgrading. Ceramic membranes are a new class of materials, which have shown promise in a variety of industrial applications. Their mechanical and chemical stability coupled with a wide range of operating temperatures and pressures make them suitable for environments found in coal liquid upgrading. In this project we wig evaluate the performance of Sel-Gel alumina membranes in coal liquid upgrading processes under realistic temperature and pressure conditions and investigate the feasibility of using such membranes in a membrane reactor based coal liquid upgrading process. In addition, the development of novel ceramic membranes with enhanced catalytic activity for coal-liquid upgrading applications, such as carbon-coated alumina membranes, will be also investigated.

  14. High temperature ceramic membrane reactors for coal liquid upgrading. Quarterly report No. 10, December 21, 1991--March 20, 1992

    SciTech Connect

    Tsotsis, T.T.

    1992-07-01

    In this project we will study a novel process concept, i.e., the use of ceramic membrane reactors in upgrading of coal model compounds and coal derived liquids. In general terms, the USC research team is responsible for constructing and operating the membrane reactor apparatus and for testing various inorganic membranes for the upgrading of coal derived asphaltenes and coal model compounds. The USC effort will involve the principal investigator of this project and two graduate research assistants. The ALCOA team is responsible for the preparation of the inorganic membranes, for construction and testing of the ceramic membrane modules, and for measurement of their transport properties. The ALCOA research effort will involve Dr. Paul K. T. Liu, who is the project manager of the ALCOA research team, an engineer and a technician. UNOCAL`s contribution will be limited to overall technical assistance in catalyst preparation and the operation of the laboratory upgrading membrane reactor and for analytical back-up and expertise in oil analysis and materials characterization. UNOCAL is a no-cost contractor but will be involved in all aspects of the project, as deemed appropriate.

  15. Short Rotation Woody Crops Program. Quarterly progress report, March 1-May 31, 1985. [Sycamore, alders, black locust, larch, poplars, saltbush

    SciTech Connect

    Wright, L.L.; Perlack, R.D.; Wenzel, C.R.; Trimble, J.L.; Ranney, J.W.

    1985-08-01

    This report covers the progress of the Short Rotation Woody Crops Program (SRWCP) during the third quarter of fiscal year 1985. This report summarizes ORNL management activities, technical activities at ORNL and subcontract institutions, and the technology transfer that is occurring as a result of subcontractor and ORNL activities. Third-year results of a nutrient utilization study confirmed that there were no benefits to quarterly fertilization with urea nitrogen. Testing of one prototype short-rotation intensive culture harvester was conducted on a sycamore plantation on Scott Paper Company land in southern Alabama. Coppice yields of European black alder reported by Iowa State University indicate potential productivity of about 7.2 dry Mg . ha/sup -1/ . year/sup -1/ if the best trees are selected. Coppice yields were more than double first-rotation yields. About 31,000 black locust and larch trees were established in 12 genetic tests at 4 sites in Michigan. Seedling rotation productivity rates of 4-year-old hybrid poplar, based on harvest data, were reported by Pennsylvania State University. Rates varied from 4.8 dry Mg . ha/sup -1/ . year/sup -1/ to 10.7 dry Mg . ha/sup -1/ . year/sup -1/, depending on site, management strategy, and planting year. An efficient method for in vitro micropropagation of elite genotypes of fourwing saltbush was developed by Plant Resources Institute. A new study to evaluate yield/density relationships was established by the USDA Forest Service, Pacific Northwest Forest and Range Experiment Station. Dissertation research on the crown geometry of plantation-grown American sycamore was completed.

  16. Catalyst and reactor development for a liquid phase Fischer-Tropsch process. Quarterly technical progress report, 1 October-31 December 1980

    SciTech Connect

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

    1981-01-01

    Air Products, under contract to the DOE, has begun a three year program in 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. Task 1 has been completed with the preparation of a Project Work Plan describing in detail the methods and technical approach to be used. Task 2 has four sub-tasks. The first segment of the background studies deals with the effect of metal particle size on product selectivity and is included in this report. Based on these background studies, ten of twenty modified traditional Fischer-Tropsch catalysts to be prepared and slurry phase tested have been identified. Slurry reactor specifications have been finalized and a comprehensive product analysis scheme and data handling system has been established. Forty of the fifty supported metal cluster catalysts to be prepared and gas phase screened have been identified. Two metal cluster catalysts have been prepared. A detailed experimental plan for the first phase of Task 3 using a 5-inch diameter cold flow reactor simulator has been completed.

  17. Final report. U.S. Department of Energy University Reactor Sharing Program

    SciTech Connect

    Bernard, John A

    2003-01-21

    Activities supported at the MIT Nuclear Reactor Laboratory under the U.S. DOE University Reactor Sharing Program are reported for Grant DE FG02-95NE38121 (September 16, 1995 through May 31, 2002). These activities fell under four subcategories: support for research at thesis and post-doctoral levels, support for college-level laboratory exercises, support for reactor tours/lectures on nuclear energy, and support for science fair participants.

  18. Consolidated fuel-reprocessing program. Quarterly progress report for the period ending November 30, 1980

    SciTech Connect

    Carney, H. C.; Pierce, V. H.; Rickman, W. S.; Strand, J. B.; Holder, N. D.; Brimhall, W. L.; Fields, D. E.; Callahan, S. F.; Higuchi, K.; Benedict, G. E.; Abraham, L.; Hirsch, P. M.; Engler, D. R.; Stock, W. C.; Wilbourn, R. G.; Dunlap, S. A.; Hostbjor, G. J.; Olquin, L. J.; Swieda, D. E.; Field, R. E.; Newman, P. W.; Rode, J. S.; Brown, L. C.; Haldy, B. B.

    1980-12-01

    Large-scale crushing and burning tests of fuel received from the Federal Republic of Germany (FRG) have identified differences in processing characteristics. The NO/sub x/ converter experimental tests continued this quarter in the GA off-gas system. The dependence of nitric oxide conversion efficiency on ammonia and oxygen concentrations has been determined. An optimum ratio of ammonia to nitric oxide was identified in terms of the conversion factor for nitrix oxide. No residual ammonia was detected downstream of the NO/sub x/ converter. Design of the radon source subsystem and fabrication of the radon source assembly and shielded radon source containment were completed. Second-thorium-cycle column tests confirm the feasibility of producing thorium product having acceptably low uranium contents. Two axial mixing tests were completed on the thorium extraction section. The Mott inertial filter tests continued. The dissolution rate of HTGR fuel spheres is speeded by a factor of three by using an airlift acid recirculator to improve ThO/sub 2/-dissolvent contact. The FRG HTGR fuel spheres dissolve a factor of three more slowly than the sol-gel derived ThO/sub 2/ spheres. The task group completed a thorium transfer kinetics comparison of alternative solvents. Hydrolysis studies were started on alternative solvents.

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

    SciTech Connect

    Benjamin, G.J.

    1994-06-01

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

  20. Base program on energy related research. Quarterly report, August 1--October 31, 1997

    SciTech Connect

    1997-12-31

    The Base Research Program at Western Research Institute (WRI) is planned to develop technologies to a level that will attract industrial sponsors for continued development under the Jointly Sponsored Research (JSR) Program. The goals of the JSR and Base Programs are accomplished by focusing research, development, demonstration, and commercialization in three major technology areas: energy programs emphasize the increased production and utilization of domestic energy resources and include enhanced oil recovery, coal beneficiation and upgrading, coalbed methane recovery, and renewable energy resources; environmental programs minimize the impact of energy production and utilization by providing technology to clean underground oily wastes, mitigate acid mine drainage, and demonstrate uses for clean coal technology (CCT) and pressurized fluidized bed combustion (PFBC) waste solids; technology enhancement activities encompass resource characterization studies, the development of improved environmental monitors and sensors, and improved techniques and models for predicting the dispersion of hazardous gas releases. Significant accomplishments under the Base Research program are reported.

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

    SciTech Connect

    Varnado, S.G.

    1980-07-01

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

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

    SciTech Connect

    Varnado, S.G.

    1980-04-01

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

  3. Geothermal drilling and completion technology development program. Quarterly progress report, October-December 1979

    SciTech Connect

    Varnado, S.G.

    1980-01-01

    The progress, status, and results of ongoing Research and Development (R and D) within the Geothermal Drilling and Completion Technology Development Program are described. The program emphasizes the development of geothermal drilling hardware, drilling fluids, and completion technology. Advanced drilling systems are also under development. The goals of the program are to develop the technology required to reduce well costs by 25% by 1982 and by 50% by 1986.

  4. DOE Safety Metrics Indicator Program (SMIP) Fiscal Year 2001 Fourth Quarter Report of Packaging- and Transportation-related Occurrences

    SciTech Connect

    Dickerson, L.S.

    2001-11-30

    The Safety Metrics Indicator Program (SMIP) retrieved 44 packaging- or transportation-related occurrences from the Occurrence Reporting and Processing System (ORPS) during the period from July 1 through September 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. Thirty-two of the originally-selected 44 occurrences were appropriate for classification to the SMIP criteria, only 7 of which have offsite applicability. Eight of the original 44 reports are archived in a subsidiary database because they either do not involve the transport of hazardous material or do not involve transport by vehicle, plane, boat, or rail. The others either were deleted because more thorough review revealed that they were not strictly related to P and T or were canceled by the reporting site and removed from the ORPS. These occurrences have not been normalized as in the Annual Report of Occurrences because the necessary information is not yet available. The number and severity of the selected occurrence reports (ORs) are consistent with historical reporting. Contamination events continue to be among the most common type of occurrences; however, ''Shipping Preparation'' events decreased this quarter to only 4 events from the 21 reported last quarter. None of the 32 ORs that were rated had event consequence measures (W{sub EC}) greater than 2; 14 of them were categorized as having a W{sub EC} of 1. This means that all of the fourth-quarter FY 2001 ORs had only slight consequences at worst (i.e., resulting in minimal safety

  5. University Reactor Sharing Program. Final report, September 30, 1992--September 29, 1994

    SciTech Connect

    Wehring, B.W.

    1995-01-01

    Over the past 20 years, the number of nuclear reactors on university campuses in the US declined from more than 70 to less than 40. Contrary to this trend, The University of Texas at Austin constructed a new reactor facility at a cost of $5.8 million. The new reactor facility houses a new TRIGA Mark II reactor which replaces an in-ground TRIGA Mark I reactor located in a 50-year old building. The new reactor facility was constructed to strengthen the instruction and research opportunities in nuclear science and engineering for both undergraduate and graduate students at The University of Texas. On January 17, 1992, The University of Texas at Austin received a license for operation of the new reactor. Initial criticality was achieved on March 12, 1992, and full power operation, on March 25, 1992. The UT-TRIGA research reactor provides hands-on education, multidisciplinary research and unique service activities for academic, medical, industrial, and government groups. Support by the University Reactor Sharing Programs increases the availability of The University of Texas reactor facility for use by other educational institutions which do not have nuclear reactors.

  6. Artificial intelligence program in a computer application supporting reactor operations

    SciTech Connect

    Stratton, R.C.; Town, G.G.

    1985-01-01

    Improving nuclear reactor power plant operability is an ever-present concern for the nuclear industry. The definition of plant operability involves a complex interaction of the ideas of reliability, safety, and efficiency. This paper presents observations concerning the issues involved and the benefits derived from the implementation of a computer application which combines traditional computer applications with artificial intelligence (AI) methodologies. A system, the Component Configuration Control System (CCCS), is being installed to support nuclear reactor operations at the Experimental Breeder Reactor II.

  7. High temperature ceramic membrane reactors for coal liquid upgrading. Quarterly report No. 11, March 21, 1992--June 20, 1992

    SciTech Connect

    Tsotsis, T.T.

    1992-12-31

    Membrane reactors have been used in a number of catalytic reaction processes in order to overcome the limitations on conversion imposed by thermodynamic equilibrium. Having the inherent capability for combining reaction and separation in a single step, they offer promise for improving and optimizing yield, selectivity and performance of processes involving complex liquids, such as these typically found in coal liquid upgrading. Ceramic membranes are a new class of materials, which have shown promise in a variety of industrial applications. Their mechanical and chemical stability coupled with a wide range of operating temperatures and pressures make them suitable for environments found in coal liquid upgrading. This project will evaluate the performance of Sol-Gel alumina membranes in coal liquid upgrading processes under realistic temperature and pressure conditions and investigate the feasibility of using such membranes in a membrane reactor based coal liquid upgrading process. Development of novel ceramic membranes with enhanced catalytic activity for coal-liquid upgrading applications, such as carbon-coated alumina membranes, will be also investigated.

  8. Program and Staffing Structures: Reactions from a Quarter-Century Worker in Compensatory Education.

    ERIC Educational Resources Information Center

    Holley, Freda M.

    This reaction paper presented at a conference on compensatory education begins with reviews of three studies prepared for the program and staffing session of the conference and dealing respectively with student-to-instructor ratios, instructional setting, and summer programs. The paper then presents the view that huge gains in achievement will not…

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

    SciTech Connect

    Kelsey, J.R.

    1981-06-01

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

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

    SciTech Connect

    Kelsey, J.R.

    1981-03-01

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

  11. 60 GHz gyrotron development program. Quarterly report No. 4, April-June 1980

    SciTech Connect

    Shively, J.F.; Grant, T.J.; Stone, D.S.; Symons, R.S.; Wendell, G.E.

    1980-01-01

    The objective of this program is to develop a microwave oscillator capable of producing 200 kW of CW output power at 60 GHz. The use of cyclotron resonance interaction is being pursued. The design and early procurement and construction phases of this program are discussed.

  12. DOE-OTM Tribology Program; Quarterly progress report, January 1991--March 1991

    SciTech Connect

    Nichols, F. A.; Michaels, A. I.

    1991-07-01

    The OTM Tribology Program supports generic, long-term, high-risk applied research and exploratory development which private enterprise will not or cannot pursue, in areas pertaining to energy conservation in the transportation sector. This report presents work in the three areas of the tribology program: extreme environment lubrication, engineered tribological interfaces, and tribology by design.

  13. Calorimetry exchange program quarterly data report for, January 1989--March 1989

    SciTech Connect

    Lyons, J.E.; McClelland, T.M.

    1996-08-01

    The goals of the calorimetry sample exchange program are to: discuss measurement differences; improve analytical methods; discuss new measurement capabilities; provide data to DOE on measurement capabilities to evaluate shipper-receiver differences; provide standardized materials as necessary; and provide a measurement control program for plutonium analysis. A sample of plutonium dioxide powder is available at each participating site for NDA analysis.

  14. Remediation and Prevention of Aggression: An Evaluation of the Regional Intervention Program over a Quarter Century.

    ERIC Educational Resources Information Center

    Strain, Phillip S.; Timm, Matthew A.

    2001-01-01

    This article presents an overview of the Regional Intervention Program (RIP) and describes ongoing studies to examine the long-term effects of behavioral skill training for parents of preschoolers who engaged in severe forms of aggression and antisocial behavior. Findings from the program indicate positive outcomes for adults and children.…

  15. Nuclear Medicine Program progress report for quarter ending September 30, 1992

    SciTech Connect

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Hasan, A.; Lambert, C.R.

    1992-12-01

    The radioiodination and in vivo evaluation of p-iodocaramiphen a muscarinic antagonist which binds with high affinity to the M[sub 1] receptor subtype in vitro are described. Biodistribution studies in female Fischer rats demonstrated that [[sup 125]I]-piodocaraminphen had significant cerebral localization, but the uptake did not demonstrate specific uptake in those cerebral regions rich in muscarinic receptors, and radioactivity washed out rapidly from the brain. In addition there was no significant blockage of activity when the rats were preinjected with quinuclidinyl benzilate. These results suggest that p-iodocaramiphen is not a good candidate for the in vivo study of M[sub 1] muscarinic receptor populations by SPECT. Because of the widespread interest and expected importance of the availability of large amounts of tungsten-188 required for the tungsten-188/rhenium-188 generator systems, we have investigated the large-scale production of tungsten-188 in the ORNL HFIR. We have also compared our production data with the theoretical production values and with experimental data available in the literature from other reactors. Tungsten-188 is produced in a fission nuclear reactor by double neutron capture of tungsten-186. The experimental yield of tungsten-188 is approximately 4 mCi/mg of tungsten-186 at the end of bombardment (EOB) in the HFIR operating at 85 MWt power for a one cycle irradiation ([approximately]21 days) at a thermal neutron flux of 2 [times] 10[sup 15] n.s[sup [minus]1]cm[sup [minus]2].

  16. Nuclear Medicine Program progress report for quarter ending September 30, 1992

    SciTech Connect

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Hasan, A.; Lambert, C.R.

    1992-12-01

    The radioiodination and in vivo evaluation of p-iodocaramiphen a muscarinic antagonist which binds with high affinity to the M{sub 1} receptor subtype in vitro are described. Biodistribution studies in female Fischer rats demonstrated that [{sup 125}I]-piodocaraminphen had significant cerebral localization, but the uptake did not demonstrate specific uptake in those cerebral regions rich in muscarinic receptors, and radioactivity washed out rapidly from the brain. In addition there was no significant blockage of activity when the rats were preinjected with quinuclidinyl benzilate. These results suggest that p-iodocaramiphen is not a good candidate for the in vivo study of M{sub 1} muscarinic receptor populations by SPECT. Because of the widespread interest and expected importance of the availability of large amounts of tungsten-188 required for the tungsten-188/rhenium-188 generator systems, we have investigated the large-scale production of tungsten-188 in the ORNL HFIR. We have also compared our production data with the theoretical production values and with experimental data available in the literature from other reactors. Tungsten-188 is produced in a fission nuclear reactor by double neutron capture of tungsten-186. The experimental yield of tungsten-188 is approximately 4 mCi/mg of tungsten-186 at the end of bombardment (EOB) in the HFIR operating at 85 MWt power for a one cycle irradiation ({approximately}21 days) at a thermal neutron flux of 2 {times} 10{sup 15} n.s{sup {minus}1}cm{sup {minus}2}.

  17. PARET-ANL. Program for the Analysis of Reactor Transients

    SciTech Connect

    Woodruff, W.L.

    1984-11-01

    PERET-ANL is designed for use in predicting the course and consequences of nondestructive reactivity accidents in research and test reactor cores. It can be used for both steady-state and transient analysis.

  18. High temperature ceramic membrane reactors for coal liquid upgrading. Quarterly report No. 2, December 21, 1989--March 20, 1990

    SciTech Connect

    Tsotsis, T.T.

    1992-06-19

    Ceramic membranes are a new class of materials, which have shown promise in a variety of industrial applications. Their mechanical and chemical stability coupled with a wide range of operating temperatures and pressures make them suitable for environments found in coal liquid upgrading. In this project we will evaluate the performance of Sel-Gel alumina membranes in coal liquid upgrading processes under realistic temperature and pressure conditions and investigate the feasibility of using such membranes in a membrane reactor based coal liquid upgrading process. In addition, the development of novel ceramic membranes with enhanced catalytic activity for coal-liquid upgrading applications, such as carbon-coated alumina membranes, will be also investigated.

  19. High temperature ceramic membrane reactors for coal liquid upgrading. Quarterly report No. 8, June 21, 1991--September 20, 1991

    SciTech Connect

    Tsotsis, T.T.

    1992-06-19

    Ceramic membranes are a new class of materials, which have shown promise in a variety of industrial applications. Their mechanical and chemical stability coupled with a wide range of operating temperatures and pressures make them suitable for environments found in coal liquid upgrading. In this project we will evaluate the performance of Sel-Gel alumina membranes in coal liquid upgrading processes under realistic temperature and pressure conditions and investigate the feasibility of using such membranes in a membrane reactor based coal liquid upgrading process. In addition, the development of novel ceramic membranes with enhanced catalytic activity for coal-liquid upgrading applications, such as carbon-coated alumina membranes, will also be investigated.

  20. High temperature ceramic membrane reactors for coal liquid upgrading. Quarterly report No. 7, March 21, 1991--June 20, 1991

    SciTech Connect

    Tsotsis, T.T.

    1992-06-19

    Ceramic membranes are a new class of materials, which have shown promise in a variety of industrial applications. Their mechanical and chemical stability coupled with a wide range of operating temperatures and pressures make them suitable for environments found in coal liquid upgrading. In this project we will evaluate the performance of Sel-Gel alumina membranes in coal liquid upgrading processes under realistic temperature and pressure conditions and investigate the feasibility of using such membranes in a membrane reactor based coal liquid upgrading process. In addition, the development of novel ceramic membranes with enhanced catalytic activity for coal-liquid upgrading applications, such as carbon-coated alumina membranes, will be also investigated.

  1. Base program on energy-related research. Quarterly report, February 1995--April 1995

    SciTech Connect

    1995-06-01

    This report describes research performed by the Morgantown Energy Technology Center in the following areas: oil and gas; advanced systems describing a coal solid fuel and an eastern shale oil residue waste program; environmental remediation; and waste management technologies.

  2. Base program on energy related research. Quarterly report, November 1, 1996--January 31, 1997

    SciTech Connect

    1997-06-01

    The Base Research Program at Western Research Institute (WRI) is planned to develop technologies to a level that will attract industrial sponsors for continued development under the Jointly Sponsored Research (JSR) Program. The goals of the Base Research Program are in support of those of the JSR Program, which are designed to: increase the production of US and western energy resources, particularly low-sulfur coal, natural gas, oil, and renewable energy resources; enhance the competitiveness of US and western energy technologies in international markets and assist in technology transfer; reduce the nation`s dependence on foreign energy supplies and strengthen both the US and regional economies; and minimize environmental impacts of energy production and utilization. Summaries are presented for 11 subtasks related to these four main goals.

  3. Fossil Energy Program. Quarterly progress report for the period ending March 31, 1985. [Nickel Iron Aluminides

    SciTech Connect

    Not Available

    1985-05-01

    This report covers progress made during the period January 1 through March 31, 1985, for research and development projects that contribute to the advancement of various fossil energy technologies. Projects on the Fossil Energy Program are supported by DOE Office of Fossil Energy, DOE Office of Basic Energy Sciences, the Electric Power Research Institute, and the Tennessee Valley Authority. The Fossil Energy Program organization chart is shown in Appendix A. Summaries and progress reports are presented for the following tasks: (1) materials research and development; (2) fossil energy environmental programs; (3) coal conversion development; (4) process analysis and development; (5) generalized equilibrium models of liquid and gaseous fuel supply; (6) fluidized bed combustion joint program; and (7) coal chemistry.

  4. Base program on energy related research. Quarterly report, February 1--April 30, 1996

    SciTech Connect

    1996-12-31

    The Base Research Program at Western Research Institute (WRI) is planned to develop technologies to a level that will attract industrial sponsors for continued development under the Jointly Sponsored Research (JSR) Program. The goals of the Base Research Program are in support of those of the JSR Program, which are designed to: increase the production of US and western energy resources, particularly low-sulfur coal, natural gas, oil, and renewable energy resources; enhance the competitiveness of US and western energy technologies in international markets and assist in technology transfer; reduce the nation`s dependence on foreign energy supplies and strengthen both the US and regional economies; and minimize environmental impacts of energy production and utilization. Summaries are presented for many of the subtasks related to oil and gas research, advanced systems applications for coal, environmental technologies, and remediation. The paper also contains federal assistance management summary reports, and contract status reports.

  5. Fossil Energy Program quarterly progress report for the period ending March 31, 1986

    SciTech Connect

    Bradley, R.A.

    1986-06-01

    This report covers progress made during the period January 1 through March 31, 1986, for research and development projects that contribute to the advancement of various fossil energy technologies. Projects on the Fossil Energy Program are supported by DOE Office of Fossil Energy, DOE Office of Basic Energy Sciences, and the Tennessee Valley Authority. The Fossil Energy Program organization chart is shown in the Appendix.

  6. Nuclear medicine program progress report for quarter ending September 30, 1996

    SciTech Connect

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Boll, R.; Luo, H.; McPherson, D.W.; Mirzadeh, S.

    1997-01-01

    The reactor production yields of tungsten-188 produced by neutron capture by enriched tungsten-186 in the HFIR and other reactors are nearly an order of magnitude lower than expected by calculation using established cross section values. Since neutron capture of tungsten-188 may be the major factor which significantly reduces the observed yields of tungsten-188, the authors have evaluated the possible burn-up cross section of the tungsten-188 product. Tungsten-189 was produced by irradiating a radioactive target containing a known amount of {sup 188}W. In order to reduce the radiation level to an acceptable level (<20% detector dead time), the authors chemically removed >90% of {sup 188}Re, which is the decay product of {sup 188}W, prior to irradiation. They were able to confirm the two predominant {gamma}-rays in the decay of {sup 189}W, 260.1 {+-} 1.4 and 421.5 {+-} 1.6 keV. By following the decay of these {gamma}-rays in two sets of experiments, a half-life of 10.8 {+-} 0.3 m was obtained for {sup 189}W. Based on a knowledge of the {sup 188}W content of target (52.6 mBq), neutron flux of 5 {times} 10{sup 13} n {center_dot} s{sup {minus}1} {center_dot} cm{sup {minus}2}, irradiation time of 10 min and with the assumption of 100% intensity for 260.1 and 421.5 keV {gamma}-rays, a cross-section of 12.0 {+-} 2.5 b was calculated for burn-up cross-section of {sup 188}W, which helps explain the greatly reduced production yields of {sup 188}W.

  7. Base program on energy related research. Quarterly report, May, 1996--July 31, 1996

    SciTech Connect

    1997-04-01

    The Base Research Program at Western Research Institute (WRI) is planned to develop technologies to a level that will attract industrial sponsors for continued development under the Jointly Sponsored Research (JSR) Program. In many instances, a potential JSR cosponsor has been identified but additional laboratory or bench-scale data are necessary to assess the utility of the technology prior to cosponsor investment. Both peer and management review are employed prior to proposing Base projects to the US DOE. The goals of the Base Research Program are in support of those of the JSR program, which are designed to: increase the production of United States and western energy resources, particularly low-sulfur coal, natural gas, oil, and renewable energy resources; enhance the competitiveness of US and western energy technologies in international markets and assist in technology transfer; reduce the nations`s dependence on foreign energy supplies and strengthen both the US and regional economies; minimize environmental impacts of energy production and utilization. The goals of the JSR and Base Programs are accomplished by focusing research, development, demonstration, and commercialization in three major technology areas: Energy Programs emphasize the increased production and utilization of domestic energy resources and include enhanced oil recovery, coal bonification and upgrading, coalbed methane recovery, and renewable energy resources; Environmental Programs minimize the impact of energy production and utilization by providing technology to clean underground oily wastes, mitigate acid mine drainage, and demonstrate uses for Clean Coal Technology and pressurized fluidized bed combustion waste solids; Technology Enhancement activities encompass resource characterization studies, the development of improved environmental monitors and sensors, and improved techniques and models for predicting the dispersion of hazardous gas releases.

  8. Northeast Regional Biomass Program. Ninth year, Fourth quarterly report, July--September 1992

    SciTech Connect

    Lusk, P.D.

    1992-12-01

    The Northeast Regional Biomass Program has been in operation for a period of nine years. During this time, state managed programs and technical programs have been conducted covering a wide range of activities primarily aim at the use and applications of wood as a fuel. These activities include: assessments of available biomass resources; surveys to determine what industries, businesses, institutions, and utility companies use wood and wood waste for fuel; and workshops, seminars, and demonstrations to provide technical assistance. In the Northeast, an estimated 6.2 million tons of wood are used in the commercial and industrial sector, where 12.5 million cords are used for residential heating annually. Of this useage, 1504.7 mw of power has been generated from biomass. The use of wood energy products has had substantial employment and income benefits in the region. Although wood and woodwaste have received primary emphasis in the regional program, the use of municipal solid waste has received increased emphasis as an energy source. The energy contribution of biomass will increase as potentia users become more familiar with existing feedstocks, technologies, and applications. The Northeast Regional Biomass Program is designed to support region-specific to overcome near-term barriers to biomass energy use.

  9. Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program

    SciTech Connect

    Smith, Cyrus M; Nanstad, Randy K; Clayton, Dwight A; Matlack, Katie; Ramuhalli, Pradeep; Light, Glenn

    2012-09-01

    The Department of Energy s (DOE) Light Water Reactor Sustainability (LWRS) Program is a five year effort which works to develop the fundamental scientific basis to understand, predict, and measure changes in materials and systems, structure, and components as they age in environments associated with continued long-term operations of existing commercial nuclear power reactors. This year, the Materials Aging and Degradation (MAaD) Pathway of this program has placed emphasis on emerging Non-Destructive Evaluation (NDE) methods which support these objectives. DOE funded Research and Development (R&D) on emerging NDE techniques to support commercial nuclear reactor sustainability is expected to begin next year. This summer, the MAaD Pathway invited subject matter experts to participate in a series of workshops which developed the basis for the research plan of these DOE R&D NDE activities. This document presents the results of one of these workshops which are the DOE LWRS NDE R&D Roadmap for Reactor Pressure Vessels (RPV). These workshops made a substantial effort to coordinate the DOE NDE R&D with that already underway or planned by the Electric Power Research Institute (EPRI) and the Nuclear Regulatory Commission (NRC) through their representation at these workshops.

  10. Electric Vehicle Site Operator Program. Year 1 third quarter report, January 1, 1992--March 31, 1992

    SciTech Connect

    Not Available

    1992-06-01

    Kansas State University, with funding support from federal, state, public, and private companies, is participating in the Department of Energy`s Electric Vehicle Site Operator Program. Through participation is this program, Kansas State is demonstrating, testing, and evaluating electric or hybrid vehicle technology. This participation 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 stationwagons.

  11. Quarterly Technical Progress Report of Radioisotope Power System Materials Production and Technology Program tasks for April 2000 through June 2000

    SciTech Connect

    Moore, J.P.

    2000-10-23

    The Office of Space and Defense Power Systems (OSDPS) of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. For the Cassini Mission, for example, ORNL was involved in the production of carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVSs) and weld shields (WSs). This quarterly report has been divided into three sections to reflect program guidance from OSDPS for fiscal year (FY) 2000. The first section deals primarily with maintenance of the capability to produce flight quality carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, clad vent sets (CVSs), and weld shields (WSs). In all three cases, production maintenance is assured by the manufacture of limited quantities of flight quality (FQ) components. The second section deals with several technology activities to improve the manufacturing processes, characterize materials, or to develop technologies for two new RPS. The last section is dedicated to studies of the potential for the production of 238Pu at ORNL.

  12. Quarterly Technical Progress Report of Radioisotope Power System Materials Production and Technology Program tasks for January 2000 through March 2000

    SciTech Connect

    Moore, J.P.

    2000-08-18

    The Office of Space and Defense Power Systems (OSDPS) of the Department of Energy (DOE) provides radioisotope Power Systems (BPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of .I 997 to study the planet Saturn. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. For the Cassini Mission, for example, ORNL was involved in the production of carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVSs) and weld shields (WSs). This quarterly report has been divided into three sections to reflect program guidance from OSDPS for fiscal year (FY) 2000. The first section deals primarily with maintenance of the capability to produce flight quality carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, clad vent sets (CVSs), and weld shields (WSs). In all three cases, production maintenance is assured by the manufacture of limited quantities of flight quality (FQ) components. The second section deals with several technology activities to improve the manufacturing processes, characterize materials, or to develop technologies for two new RPS. The last section is dedicated to studies of the potential for the production of 238Pu at OBNL.

  13. Fluidized-bed combustion process evaluation and program support. Quarterly report, October-December 1979

    SciTech Connect

    Johnson, I.; Podolski, W.F.; Henry, R.F.; Hanway, J.E.; Griggs, K.E.; Carls, E.L.; Jonke, A.A.

    1980-01-01

    Argonne National Laboratory is undertaking several tasks primarily in support of the pressurized fluidized-bed combustion (PFBC) project management team at Morgantown Energy Technology Center (METC). The Experimental Program Director of the International Energy Agency pressurized fluidized-bed combustion project was selected. Work is under way to provide fluidized-bed combustion process evaluation and program support to METC, including development of a planning methodology for PFBC technology development, determination of the state of the art of instrumentation for FBC applications, and evaluation of the performance capability of cyclones for hot-gas cleaning in PFBC systems.

  14. Advanced reactors transition fiscal year 1995 multi-year program plan WBS 7.3

    SciTech Connect

    Loika, E.F.

    1994-09-22

    This document describes in detail the work to be accomplished in FY-1995 and the out years for the Advanced Reactors Transition (WBS 7.3). This document describes specific milestones and funding profiles. Based upon the Fiscal Year 1995 Multi-Year Program Plan, DOE will provide authorization to perform the work outlined in the FY 1995 MYPP. Following direction given by the US Department of Energy (DOE) on December 15, 1993, Advanced Reactors Transition (ART), previously known as Advanced Reactors, will provide the planning and perform the necessary activities for placing the Fast Flux Test Facility (FFTF) in a radiologically and industrially safe shutdown condition. The DOE goal is to accomplish the shutdown in approximately five years. The Advanced Reactors Transition Multi-Year Program Plan, and the supporting documents; i.e., the FFTF Shutdown Program Plan and the FFTF Shutdown Project Resource Loaded Schedule (RLS), are defined for the life of the Program. During the transition period to achieve the Shutdown end-state, the facilities and systems will continue to be maintained in a safe and environmentally sound condition. Additionally, facilities that were associated with the Office of Nuclear Energy (NE) Programs, and are no longer required to support the Liquid Metal Reactor Program will be deactivated and transferred to an alternate sponsor or the Decontamination and Decommissioning (D and D) Program for final disposition, as appropriate.

  15. Educational Technology Program. Quarterly Technical Summary, Period Ending 31 May 1970.

    ERIC Educational Resources Information Center

    Frick, Frederick C.

    An overview of the Lincoln Training System (LTS) and descriptions of the hardward and software of the LTS-1 and LTS-2 systems are provided. The overall program seeks to develop, test, and evaluate technical aids to vocational training systems. These are appropriate to this field because the high costs need to be reduced and because there are clear…

  16. Library Service Enhancement Program, DePauw University. Grant Proposal and Quarterly Reports.

    ERIC Educational Resources Information Center

    Martindale, James; Hardesty, Larry

    The purpose of this grant, funded by the Council on Library Resources, was to allow a librarian to put aside normal duties for an academic year to explore with faculty, students, and administrators ways of improving library services, and to design methods of increasing library use by college students. A program was developed for orienting and…

  17. Fossil Energy Program. Quarterly progress report for the period ending December 31, 1985

    SciTech Connect

    Bradley, R.A.

    1986-03-01

    This report covers progress made during the period October 1 through December 31, 1985, for research and development projects that contribute to the advancement of various fossil energy technologies. Projects on the Fossil Energy Program are supported by DOE Office of Fossil Energy, DOE Office of Basic Energy Sciences, and the Tennessee Valley Authority.

  18. Fossil Energy Program. Quarterly progress report for the period ending September 30, 1985

    SciTech Connect

    Bradley, R.A.

    1985-12-01

    This report covers progress made during the period July 1 through September 30, 1985, for research and development projects that contribute to the advancement of various fossil energy technologies. Projects on the Fossil Energy Program are supported by DOE Office of Fossil Energy, DOE Office of Basic Energy Sciences, the Electric Power Research Institute, and the Tennessee Valley Authority.

  19. Peat biogasification development program. Quarterly progress report No. 2, January 1-March 31, 1980

    SciTech Connect

    Wise, Donald L.; Buivid, Michael G.

    1980-01-01

    Batch experiments have been performed to determine the effects of different alkalis, temperatures, retention times, solids loading, and oxygen partial pressures on the solubility of peat organic material. Oxidation experiments have been performed simultaneously with and separately from solubilization. In both cases kinetic information has been developed based on oxygen consumption. Kinetics based on fermentable product formation are dependent on satisfactory identification methods. Development of analytical procedures for product identification have included: Gel Permeation Chromatography (GPC), solvent extraction, aldehyde precipitation, and Thin Layer Chromatography (TLC). Microorganisms from three inoculation sources are being grown anaerobically using a growth medium containing a standard nutrient and a specific substrate, one of twelve aromatic compounds. The concentration of aromatic compound was increased gradually in order that bacteria acclimate for future use as inocula with pretreated peat liquors. Acids and methane production are being monitored for pretreated peat liquor fermentations using an acclimated microorganism inocula. Apparent viscosity and apparent heat transfer coefficient data are being obtained at three peat slurry solids concentrations (3-5, 10, 15% total solids). A 75% heat recovery would give a positive energy balance around the pretreatment reactor. Development has continued in regards to full scale peat biogasification design (75 x 10/sup 6/ SCFD, pipeline quality methane). The information necessary for continuous PDU scale operation is being evaluated in terms of what processing information may be obtained from various scale units, batch and continuous.

  20. Catalyst and reactor development for a liquid-phase Fischer-Tropsch process. Quarterly technical progress report, 1 October 1982-31 December 1982

    SciTech Connect

    Dyer, P.N.; Pierantozzi, R.; Brian, B.W.; Bauer, J.V.; Parsons, R.L.

    1983-03-01

    Two major tasks were continued: (1) Slurry Catalyst Development, and (2) Slurry Reactor Design Studies. The first extended slurry test was begun, using a proprietary catalyst. High selectivities and large deviations from the Schulz-Flory distribution were observed. A bulk activity 2.5 times greater than the baseline Fe/sub 2/O/sub 3/ was determined, with little deactivation over 450 h. Consistently low CH/sub 4/ yields of 3 to 5 wt %, and high C/sub 9/-C/sub 25/ fractions of 45 to 50 wt %, were produced at 240/sup 0/C, 300 psig and 1:1 CO/H/sub 2/. This test is being continued with higher CO/H/sub 2/ ratios and operating temperatures. Parametric gas phase screening studies were concluded for two further modified conventional catalysts and the optimum preparations in terms of activity and diesel range selectivity were chosen for subsequent slurry phase testing. Gas holdup and solid concentration profiles were measured for water/silica slurries in the 5'' column, and for paraffin/silica slurries in the 12'' column, both with and without heat transfer internals. In both columns, gas holdup was found to be close to the Akita and Yoshida correlation. Very non-uniform solid concentration profiles were observed in the 2 column for the 90 to 115 ..mu..m size silica, with settling of the slurry on the distributor plate. Smaller size particles were more uniformly distributed. Heat transfer coefficients were determined in the 12'' column for paraffin/silica slurries, using seven vertical, tubular heat transfer elements. The values were in good agrement with Deckwer's correlation for the large and medium size particles, but were lower for the 0.5 to 5 ..mu..m size range. The bubble size diameter probe was successfully calibrated using a strobe technique, and data acquisition will begin next quarter.

  1. Combined shift and methanation in a fluidized-bed reactor. Quarterly progress report, 1 April-30 June 1980

    SciTech Connect

    Streeter, R C

    1980-07-01

    Only one bench-scale reactor test was completed. The Harshaw Ni/Cu/Mo and UCI (composition undisclosed) catalysts were evaluated over a 12-day period at 800 F and a feed gas H/sub 2//CO ratio of 2/1. Initial conversions with both catalysts were about 33 percent; and the activities of both samples declined steadily during the test, with final conversion values in the 15 to 20 percent range. During this test, problems were experienced with water carryover into the Drierite traps, necessitating some major design changes in the water letdown system. Two subsequent attempts to initiate a second test at 950 F with these catalysts were unsuccessful for the reasons given. A 5-day PEDU test (Test SM-2) was conducted using the spent Harshaw Ni/Cu/Mo catalyst from Test SM-1 in February. The purpose was to continue the data period at H/sub 2//CO = 1/1 that was terminated prematurely during the earlier PEDU test. After a brief baseline period (H/sub 2//CO = 3/1), during which catalyst activity appeared to be normal, the feed gas was changed to approximately 31 percent H/sub 2/, 31 percent CO, 22 percent CO/sub 2/, and 16 percent CH/sub 4/; and steam was added to the feed. Some difficulty was experienced in maintaining high bed temperatures, with the result that the steam flow had to be gradually decreased. This may have enhanced catalyst coking, since the catalyst activity generally declined slowly throughout the test, and the final carbon content of the catalyst was 3.6 percent (vs. 2.0 percent at the beginning of the test). A second 5-day PEDU test (Test SM-3) was conducted using the Climax Ni/Mo catalyst. The results are described.

  2. Reactor Safety Research: Semiannual report, January-June 1986: Reactor Safety Research Program

    SciTech Connect

    Not Available

    1987-05-01

    Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the technology base supporting licensing decisions.

  3. Acid rain program: CEMS submission instructions for monitoring plans, certification test notifications, and quarterly reports

    SciTech Connect

    1995-05-12

    The Acid Rain Program regulations require all affected utility units to continuously measure, record and report SO2, NOx, volumetric flow data and CO2 emissions. All affected units also must continuously measure and record opacity, and must report opacity exceedances to the appropriate State or Local Agency. To ensure that your CEMS and fuel flowmeters are performing at an acceptable level, and providing quality assured data, you are required under 40 CFR 75.53, 75.62 (a) to submit a monitoring plan and certification test data for acid rain CEM certificaton. The purpose of this handbook is to help you fulfill your requirements under the Acid Rain Program. This handbook will walk you through the necessary steps for gaining CEMS certification, including filling out and mailing the proper forms, administering the required tests, and applying for certification and sending in electronic data to EPA.

  4. Advanced turbine systems program conceptual design and product development. Quarterly report, August--October, 1994

    SciTech Connect

    1995-01-01

    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. During this report period, the following tasks were completed: Market study; System definition and analysis; and Integrated program plans. Progress on Task 8, Design and Test of Critical Components, is also discussed. This particular task includes expanded materials and component research covering recuperators, combustion, autothermal fuel reformation, ceramics application and advanced gas turbine system controls.

  5. Coal-gasification-instrumentation program (PR 11734). Quarterly progress report, October 1, 1981-December 31, 1981

    SciTech Connect

    1982-01-12

    Research programs involving coherent anti-Stokes Raman and infrared spectroscopy techniques to measure the concentrations of minority species in coal gasification streams are considered. Equipment modifications to improve the spectral quality (lower line widths), fundamental studies of spectral lines of gases of interest, detection limits and a study of possible interferences (including subtracting some of these) are presented. Some studies involve laser-induced breakdown spectroscopy. This work involves two pulsed lasers and a timing system to introduce the appropriate delay. (LTN)

  6. Fluidized-bed combustion process evaluation and program support. Quarterly report, January-March 1980

    SciTech Connect

    Johnson, I.; Podolski, W.F.; Swift, W.M.; Henry, R.F.; Hanway, J.E.; Griggs, K.E.; Herzenberg, C.; Helt, J.E.; Carls, E.L.

    1980-12-01

    Argonne National Laboratory is undertaking several tasks primarily in support of the pressurized fluidized-bed combustion project management team at Morgantown Energy Technology Center. Work is under way to provide fluidized-bed combustion process evaluation and program support to METC, determination of the state of the art of instrumentation for FBC applications, evaluation of the performance capability of cyclones for hot-gas cleaning in PFBC systems, and an initial assessment of methods for the measurement of sodium sulfate dew point.

  7. The Savannah River Site`s Groundwater Monitoring Program. Second quarter 1994

    SciTech Connect

    Not Available

    1994-11-01

    This document contains information concerning the groundwater monitoring program at Savannah River Plant. The EPD/EMS (environmental protection department/environmental monitoring section) is responsible for monitoring constituents in the groundwater at approximately 135 waste sites in 16 areas at SRS. This report consolidates information from field reports, laboratory analysis, and quality control. The groundwater in these areas has been contaminated with radioactive materials, organic compounds, and heavy metals.

  8. Northeast regional biomass program. Second & third quarterly reports, October 1, 1995--March 31, 1996

    SciTech Connect

    1996-07-01

    The Northeast Regional Biomass Program (NRBP) is comprised of the following states: Connecticut. Delaware, Maine, Maryland, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania, Rhode Island and Vermont. It is managed for the Department of Energy (DOE) by the CONEG Policy Research Center, Inc. The Northeast states face several near-term barriers to the expanded use of biomass energy. Informational and technical barriers have impeded industrial conversions, delaying the development of a wood energy supply infrastructure. Concern over the environmental impacts on resources are not well understood. Public awareness and concern about safety issues surrounding wood energy use has also grown to the point of applying a brake to the trend of increases in residential applications of biomass energy. In addition, many residential, industrial, and commercial energy users are discouraged from using biomass energy because of the convenience factor. Regardless of the potential for cost savings, biomass energy sources, aside from being perceived as more esoteric, are also viewed as more work for the user. The Northeast Regional Biomass Program (NRBP) is designed to help the eleven Northeastern states overcome these obstacles and achieve their biomass energy potentials. The objective of this program in the current and future years is to increase the role of biomass fuels in the region`s energy mix by providing the impetus for states and the private sector to develop a viable Northeast biomass fuels market.

  9. DOE/KEURP Site Operator Program year 5 first quarter report, July 1-- September 30, 1995

    SciTech Connect

    1995-12-01

    Kansas State University, with funding support from federal, state, public, and private companies, is participating in the Department of Energy` s Electric Vehicle Site Operator Program. Through participation in this program, Kansas State is displaying, testing, and evaluating electric or hybrid vehicle technology. This participation will provide organizations the opportunity to examine the latest EHV prototypes under actual operating conditions. KSU now has two electric cars. Both are electric conversion vehicles from Soleq Corporation out of Chicago. KSU in conjunction with KEURP also initiated procurement for the purchase of four (4) Chevy S-10 pickup trucks. Since the supplier, GE-Spartan, canceled its effort concerning the production of vehicles other appropriate sources were sought. Today, K-State and the Kansas Utilities are working with Troy Design and Manufacturing (TDM), Redford, Michigan. TDM is working with Ford Motor Company and expects to become the first certified electric vehicle Quality Vehicle Modifier (QVM). Kansas State has entered into an agreement to assist TDM in supporting the infrastructure and technical manual development for these vehicles. The Soleq EVcorts have not been signed to illustrate to the public that it is an electric vehicle. Magnetic signs have been made for special functions to ensure sponsor support is recognized and acknowledged. As soon as TDM`s Ford Ranger electric vehicles are delivered they will be used throughout the state by utility companies that are participating with K-State`s Site Operator Program.

  10. Northeast Regional Biomass Program first and second quarter reports, October 1, 1994--March 31, 1995

    SciTech Connect

    1995-07-01

    The Northeast states face several near-term barriers to the expanded use of biomass energy. Informational and technical barriers have impeded industrial conversions, delaying the development of a wood energy supply infrastructure. Concern over the environmental impacts on resources are not well understood. Public awareness and concern about safety issues surrounding wood energy use has also grown to the point of applying a brake to the trend of increases in residential applications of biomass energy. In addition, many residential commercial, industrial, and commercial energy users are discouraged from using biomass energy because of the convenience factor. Regardless of the potential for cost savings, biomass energy sources, aside from being perceived as more esoteric, are also viewed as more work for the user. The Northeast Regional biomass Program (NRBP) is designed to help the eleven Northeastern states overcome these obstacles and achieve their biomass energy potentials. The objective of this program in the current and future years is to increase the role of biomass fuels in the region`s energy mix by providing the impetus for states and the private sector to develop a viable Northeast biomass fuels market. This paper contains a management report, state program summaries, technical project status report, and technology transfer activities.

  11. DOE/KEURP site operator program. Year 3, Second Quarter Report, October 1--December 31, 1993

    SciTech Connect

    Not Available

    1993-12-31

    Kansas State University, with funding support from federal, state, public, and private companies, is participating in the Department of Energy`s Electric Vehicle Site Operator Program. Through participation in this program, Kansas State is displaying, testing, and evaluating electric or hybrid vehicle technology. This participation will provide organizations the opportunity to examine the latest EHV prototypes under actual operating conditions. KSU has purchased several electric cars and proposes to purchase additional electric vehicles. KSU has purchased one G-Van built by Conceptor Industries, Toronto, Canada and has procured two (2) Soleq 1993 Ford EVcort station wagons. During calendar year 1994, the Kansas` electric vehicle program expects to purchase a minimum of four and a maximum of eleven additional electric vehicles. The G-Van was signed in order for the public to be aware that it was an electric vehicle. Financial participants` names have been stenciled on the back door of the van. The Soleq EvCorts have not been signed. In order to demonstrate the technology as feasible, the EvCorts were deliberately not signed. The goal is to generate a public perception that this vehicle is no different from any similar internal combustion engine vehicle. Magnetic signs have been made for special functions to ensure sponsor support is recognized and acknowledged.

  12. Benchmark Evaluation of the Medium-Power Reactor Experiment Program Critical Configurations

    SciTech Connect

    Margaret A. Marshall; John D. Bess

    2013-02-01

    A series of small, compact critical assembly (SCCA) experiments were performed in 1962-1965 at the Oak Ridge National Laboratory Critical Experiments Facility (ORCEF) for the Medium-Power Reactor Experiment (MPRE) program. The MPRE was a stainless-steel clad, highly enriched uranium (HEU)-O2 fuelled, BeO reflected reactor design to provide electrical power to space vehicles. Cooling and heat transfer were to be achieved by boiling potassium in the reactor core and passing vapor directly through a turbine. Graphite- and beryllium-reflected assemblies were constructed at ORCEF to verify the critical mass, power distribution, and other reactor physics measurements needed to validate reactor calculations and reactor physics methods. The experimental series was broken into three parts, with the third portion of the experiments representing the beryllium-reflected measurements. The latter experiments are of interest for validating current reactor design efforts for a fission surface power reactor. The entire series has been evaluated as acceptable benchmark experiments and submitted for publication in the International Handbook of Evaluated Criticality Safety Benchmark Experiments and in the International Handbook of Evaluated Reactor Physics Benchmark Experiments.

  13. Plutonium Consumption Program, CANDU Reactor Project final report

    SciTech Connect

    Not Available

    1994-07-31

    DOE is investigating methods for long term dispositioning of weapons grade plutonium. One such method would be to utilize the plutonium in Mixed OXide (MOX) fuel assemblies in existing CANDU reactors. CANDU (Canadian Deuterium Uranium) reactors are designed, licensed, built, and supported by Atomic Energy of Canada Limited (AECL), and currently use natural uranium oxide as fuel. The MOX spent fuel assemblies removed from the reactor would be similar to the spent fuel currently produced using natural uranium fuel, thus rendering the plutonium as unattractive as that in the stockpiles of commercial spent fuel. This report presents the results of a study sponsored by the DOE for dispositioning the plutonium using CANDU technology. Ontario Hydro`s Bruce A was used as reference. The fuel design study defined the optimum parameters to disposition 50 tons of Pu in 25 years (or 100 tons). Two alternate fuel designs were studied. Safeguards, security, environment, safety, health, economics, etc. were considered. Options for complete destruction of the Pu were also studied briefly; CANDU has a superior ability for this. Alternative deployment options were explored and the potential impact on Pu dispositioning in the former Soviet Union was studied. An integrated system can be ready to begin Pu consumption in 4 years, with no changes required to the reactors other than for safe, secure storage of new fuel.

  14. US Department of Energy Office of Civilian Radioactive Waste Management quarterly report on program cost and schedule; First quarter, FY 1992

    SciTech Connect

    1992-07-01

    This report is intended to provide a summary of the cost and schedule performance for the Civilian Radioactive Waste Management Program. Historical 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 December 1991.

  15. Advanced Turbine Systems Program conceptual design and product development. Quarterly report, November 1994--January 1995

    SciTech Connect

    1995-02-01

    Objective of Phase II of the ATS Program is to provide the conceptual design and product development plan for anultra high efficiency, environmentally superior and cost competitive industrial gas turbine system to be commercialized by the year 2000. Technical progress covered in this report is confined to Task 4 (conversion to coal) and the nine subtasks under Task 8 (design and test of critical components). These nine subtasks address six ATS technologies: catalytic combustion, recuperator, autothermal fuel reformer, high temperature turbine disc, advanced control system, and ceramic materials.

  16. Advanced turbine systems program conceptual design and product development. Quarterly report, August--October 1995

    SciTech Connect

    1996-01-01

    This report describes the tasks completed for the advanced turbine systems program. The topics of the report include last row turbine blade development, single crystal blade casting development, ceramic materials development, combustion cylinder flow mapping, shroud film cooling, directional solidified valve development, shrouded blade cooling, closed-loop steam cooling, active tip clearance control, flow visualization tests, combustion noise investigation, TBC field testing, catalytic combustion development, optical diagnostics probe development, serpentine channel cooling tests, brush seal development, high efficiency compressor design, advanced air sealing development, advanced coating development, single crystal blade development, Ni-based disc forging development, and steam cooling effects on materials.

  17. Providing solutions to energy and environmental programs. Quarterly report, October 1--December 31, 1996

    SciTech Connect

    1996-12-31

    The goals of WRI`s jointly sponsored research program are to: (1) increase the production of US and western energy resources--low-sulfur coal, natural gas, oil, and renewable energy resources; (2) enhance the competitiveness of US and western energy technologies in international markets and assist in technology transfer; (3) reduce the nation`s dependence upon foreign energy supplies and strengthen the US and regional economies; and (4) minimize the impact of energy production and utilization on the environment. A summary of appropriations, obligations and expenditures is given, then a summary of objectives and accomplishments for the 21 tasks being supported is presented.

  18. Advanced Reactors Transition program fiscal year 1998 multi-year work plan

    SciTech Connect

    Gantt, D.A.

    1997-09-25

    The mission of the Advanced Reactors Transition program is two-fold. First, the program is to maintain the Fast Flux Test Facility (FFTF) and the Fuels and Materials Examination Facility (FMEF) in Standby to support a possible future role in the tritium production strategy. Secondly, the program is to continue deactivation activities which do not conflict with the Standby directive. On-going deactivation activities include the processing of non-usable, irradiated, FFTF components for storage or disposal; deactivation of Nuclear Energy legacy test facilities; and deactivation of the Plutonium Recycle Test Reactor (PRTR) facility, 309 Building.

  19. Nuclear Technology Series. Nuclear Reactor (Plant) Operator Trainee. A Suggested Program Planning Guide. Revised June 80.

    ERIC Educational Resources Information Center

    Center for Occupational Research and Development, Inc., Waco, TX.

    This program planning guide for a two-year postsecondary nuclear reactor (plant) operator trainee program is designed for use with courses 1-16 of thirty-five in the Nuclear Technology Series. The purpose of the guide is to describe the nuclear power field and its job categories for specialists, technicians and operators; and to assist planners,…

  20. Northeast regional biomass program: Second and Third quarterlies and final report, January 1994--September 30, 1994

    SciTech Connect

    1995-07-01

    The Northeast Regional Biomass Program (NRBP) is comprised of the following states: Connecticut, Delaware, Maine, Maryland, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania. Rhode Island and Vermont. It is managed for the Department of Energy (DOE) by the CONEG Policy Research Center, Inc. The Northeast states face several near-term barriers to the expanded use of biomass energy. Informational and technical barriers have impeded industrial conversions, delaying the development of a wood energy supply infrastructure. Concern over the environmental impacts on resources are not well understood. Public awareness and concern about safety issues surrounding wood energy use has also grown to the point of applying a brake to the trend of increases in residential applications of biomass energy. In addition, many residential, commercial, industrial, and commercial energy users are discouraged from using biomass energy because of the convenience factor. Regardless of the potential for cost savings, biomass energy sources, aside from being perceived as more esoteric, are also viewed as more work for the user. The Northeast Regional Biomass Program (NRBP) is designed to help the eleven states overcome obstacles and achieve biomass energy potentials.

  1. Quarterly Progress Report on the Biological Monitoring Program for East Fork Poplar Creek

    SciTech Connect

    Adams, S.M.; Ashwood, T.L.; Cicerone, D.S.; Greeley, M.S. Jr.; Hill, W.R.; Kszos, L.A.

    1996-12-30

    In May 1985, a National Pollutant Discharge Elimination System (NPDES) permit was issued for the Oak Ridge Y-12 Plant. As a condition of the permit, a Biological Monitoring and Abatement Program ( BMAP) was developed to demonstrate that the effluent limitations established for the Y-12 Plant protect the classified uses of the receiving stream (East Fork Poplar Creek; EFPC), in particular, the growth and propagation of aquatic life (Lear et al. 1989). A second objective of the BMAP is to document the ecological effects resulting from the implementation of a water pollution control program designed to eliminate direct discharges of wastewaters to EFPC and to minimize the inadvertent release of pollutants to the environment. Because of the complex nature of the discharges to EFPC and the temporal and spatial variability in the composition of the discharges, a comprehensive, integrated approach to biological monitoring was developed. A new permit was issued to the Y-12 Plant on April 28, 1995 and became effective on July 1, 1995. Biological monitoring continues to be required under the new permit. The BMAP consists of four major tasks that reflect different but complementary approaches to evaluating the effects of the Y-12 Plant discharges on the aquatic integrity of EFPC. These tasks are (1) toxicity monitoring, (2) biological indicator studies, (3) bioaccumulation studies, and (4) ecological surveys of the periphyton, benthic macroinvertebrate, and fish communities.

  2. Decontamination Systems Information and Research Program. Quarterly report, October--December 1993

    SciTech Connect

    Not Available

    1994-02-01

    This report is a summary of the work conducted for the period of October--December 1993 by the West Virginia University for the US DOE Morgantown Energy Technology Center. Research under the program focuses on pertinent technology for hazardous waste clean-up. This report reflects the progress performed on sixteen technical projects encompassed by this program: Systematic assessment of the state of hazardous waste clean-up technologies; Site remediation technologies: (a) Drain-enhanced soil flushing and (b) In situ bio-remediation of organic contaminants; Excavation systems for hazardous waste sites: Dust control methods for in-situ nuclear waste handling; Chemical destruction of polychlorinated biphenyls; Development of organic sensors: Monolayer and multilayer self-assembled films for chemical sensors; Winfield lock and dam remediation; Assessment of technologies for hazardous waste site remediation: Non-treatment technologies and pilot scale test facility implementation; Remediation of hazardous sites with steam reforming; Microbial enrichment for enhancing biodegradation of hazardous organic wastes in soil; Soil decontamination with a packed flotation column; Treatment of volatile organic compounds using biofilters; Use of granular activated carbon columns for the simultaneous removal of organic, heavy metals, and radionuclides; Compact mercuric iodide detector technology development; Evaluation of IR and mass spectrometric techniques for on-site monitoring of volatile organic compounds; and Improved socio-economic assessment of alternative environmental restoration techniques.

  3. Decontamination systems information and research program. Quarterly report, April--June 1996

    SciTech Connect

    1996-07-01

    This report contains separate reports on the following subtasks: analysis of the Vortec cyclone melting system for remediation of PCB contaminated soils using CFD; drain enhanced soil flushing using prefabricated vertical drains; performance and characteristics evaluation of acrylates as grout barriers; development of standard test protocol barrier design models for desiccation barriers, and for in-situ formed barriers; in-situ bioremediation of chlorinated solvents at Portsmouth Gaseous Diffusion Plant; development of a decision support system and a prototype database for management of the EM50 technology development program; GIS-based infrastructure for site characterization and remediation; treatment of mixed wastes via fluidized bed steam reforming; use of centrifugal membrane technology to treat hazardous/radioactive waste; environmental pollution control devices based on novel forms of carbon; development of instrumental methods for analysis of nuclear wastes and environmental materials; production and testing of biosorbents and cleaning solutions for D and D; use of SpinTek centrifugal membrane and sorbents/cleaning solutions for D and D; West Virginia High Tech Consortium Foundation--Environmental support program; small business interaction opportunities; and approach for assessing potential voluntary environmental protection.

  4. 75 FR 58789 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-April Through June 2010

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-24

    ...This notice lists CMS manual instructions, substantive and interpretive regulations, and other Federal Register notices that were published from April through June 2010, relating to the Medicare and Medicaid programs. This notice provides information on national coverage determinations (NCDs) affecting specific medical and health care services under Medicare. Additionally, this notice......

  5. 75 FR 14905 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-October Through December 2009

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-26

    ...This notice lists CMS manual instructions, substantive and interpretive regulations, and other Federal Register notices that were published from October 2009 through December 2009, relating to the Medicare and Medicaid programs. This notice provides information on national coverage determinations (NCDs) affecting specific medical and health care services under Medicare. Additionally, this......

  6. Progress in space nuclear reactor power systems technology development - The SP-100 program

    NASA Technical Reports Server (NTRS)

    Davis, H. S.

    1984-01-01

    Activities related to the development of high-temperature compact nuclear reactors for space applications had reached a comparatively high level in the U.S. during the mid-1950s and 1960s, although only one U.S. nuclear reactor-powered spacecraft was actually launched. After 1973, very little effort was devoted to space nuclear reactor and propulsion systems. In February 1983, significant activities toward the development of the technology for space nuclear reactor power systems were resumed with the SP-100 Program. Specific SP-100 Program objectives are partly related to the determination of the potential performance limits for space nuclear power systems in 100-kWe and 1- to 100-MW electrical classes. Attention is given to potential missions and applications, regimes of possible space power applicability, safety considerations, conceptual system designs, the establishment of technical feasibility, nuclear technology, materials technology, and prospects for the future.

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

    SciTech Connect

    DL Sisterson

    2006-10-01

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

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

    SciTech Connect

    DL Sisterson

    2006-07-01

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

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

    SciTech Connect

    DL Sisterson

    2008-09-30

    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 (FY) dating back to 1998.

  10. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report April 1 - June 30, 2008

    SciTech Connect

    DL Sisterson

    2008-06-01

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

  11. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report April 1 - June 30, 2007

    SciTech Connect

    DL Sisterson

    2007-07-01

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

  12. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report - October 1 - December 31, 2008

    SciTech Connect

    Sisterson, DL

    2009-01-15

    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 (FY) dating back to 1998.

  13. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report January 1 – March 31, 2007

    SciTech Connect

    DL Sisterson

    2007-04-01

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

  14. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report - January 1 - March 31, 2008

    SciTech Connect

    Sisterson, DL

    2008-04-01

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

  15. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report October 1 - December 31, 2007

    SciTech Connect

    DL Sisterson

    2008-01-08

    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 (FY) dating back to 1998.

  16. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report January 1 - March 31, 2009

    SciTech Connect

    DL Sisterson

    2009-03-17

    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.

  17. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report July 1 - September 30, 2007

    SciTech Connect

    DL Sisterson

    2007-10-01

    Description. Individual raw data streams from instrumentation at the Atmospheric Radiation Measurement (ARM) Program Climate Research Facility (ACRF) fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at Pacific Northwest National Laboratory (PNNL) for processing in near real time. Raw and processed data are then sent daily to the ARM 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.

  18. Long term materials test program. Quarterly report, April-June 1983

    SciTech Connect

    Not Available

    1984-01-01

    Corrosion and erosion/corrosion testing of gas turbine materials in the effluent from a pressurized fluidized bed coal combustor continues under the Long Term Materials Test program. Two 1000-hour erosion/corrosion screening tests of twelve candidate gas turbine vane and blade base alloys and a variety of protective coating systems have been completed. Test conditions included 1350/sup 0/F, 800 to 900 ft/s and particulate loadings of 30 to 90 ppM. Erosion/corrosion degradation rates of 1 to 4 mils/1000 hours were observed with corrosion predominant in areas of particle impaction. FeCrAlY, CoCrAlY and rhodium aluminide coatings show significantly better resistance to degradation than unprotected base alloys, aluminide or platinum-aluminide diffusion coatings.

  19. A Year of Radiation Measurements at the North Slope of Alaska Second Quarter 2009 ARM and Climate Change Prediction Program Metric Report

    SciTech Connect

    S.A. McFarlane, Y. Shi, C.N. Long

    2009-04-15

    In 2009, the Atmospheric Radiation Measurement (ARM) Program and the Climate Change Prediction Program (CCPP) have been asked to produce joint science metrics. For CCPP, the second quarter metrics are reported in Evaluation of Simulated Precipitation in CCSM3: Annual Cycle Performance Metrics at Watershed Scales. For ARM, the metrics will produce and make available new continuous time series of radiative fluxes based on one year of observations from Barrow, Alaska, during the International Polar Year and report on comparisons of observations with baseline simulations of the Community Climate System Model (CCSM).

  20. Participation in the United States Department of Energy Reactor Sharing Program

    SciTech Connect

    Mulder, R.U.; Benneche, P.E.; Hosticka, B.

    1992-12-01

    The University of Virginia Reactor Facility is an integral part of the Department of Mechanical, Aerospace and Nuclear Engineering and is used to support educational programs in engineering and science at the University of Virginia and at other area colleges and universities. The University of Virginia Research Reactor (UVAR) is the highest power (two megawatts thermal power) and one of the most utilized university research reactor in the mid-Atlantic states. A major objective of this facility is to support educational programs in the region. The University of Virginia has received support under the US Department of Energy (DOE) Reactor Sharing Program every year since 1978 to assist in meeting this objective. This report documents the major educational accomplishments under the Reactor Sharing Program for the period September 1991 through August 1992. This report is also to final report under this contract. Previous annual reports should be consulted if any information from those periods is desired. Additional information about the programs conducted at UVA under this contract may be found in the yearly requests for additional funds which have been submitted.

  1. Using low-enriched uranium in research reactors: The RERTR program

    SciTech Connect

    Travelli, A.

    1994-05-01

    The goal of the RERTR program is to minimize and eventually eliminate use of highway enriched uranium (HEU) in research and test reactors. The program has been very successful, and has developed low-enriched uranium (LEU) fuel materials and designs which can be used effectively in approximately 90 percent of the research and test reactors which used HEU when the program began. This progress would not have been possible without active international cooperation among fuel developers, commercial vendors, and reactor operators. The new tasks which the RERTR program is undertaking at this time include development of new and better fuels that will allow use of LEU fuels in all research and test reactors; cooperation with Russian laboratories, which will make it possible to minimize and eventually eliminate use of HEU in research reactors throughout the world, irrespective of its origin; and development of an LEU-based process for the production of {sup 99}Mo. Continuation and intensification of international cooperation are essential to the achievement of the ultimate goals of the RERTR program.

  2. (Shippingport Atomic Power Station). Quarterly operating report, third quarter 1980

    SciTech Connect

    Zagorski, J. F.

    1980-01-01

    At the beginning of the third quarter of 1980, the Shippingport Atomic Power Station was operating with the 1A, 1B, 1C, and 1D reactor coolant loops and the 1AC and 1BD purification loops in service. During the quarter, the Station was operated for Duquesne Light Company System grid including base load and swing load operation. Twelve (12) planned swing load operations were performed on the LWBR Core this quarter to complete the LWBR operating plan of fifty (50) during this operating phase. The Station was shutdown on September 12 for the Fall 1980 Shutdown and remained in this mode through the end of the quarter. The LWBR Core has generated 18,297.98 EFPH from start-up through the end of the quarter. There were no radioactive liquid discharges from the Radioactive Waste Processing System to the river this quarter. The radioactive liquid waste effluent line to the river remained blanked off to prevent inadvertent radioactive liquid waste discharges. During the quarter, approximately 0.001 curies of Xe 133 activity were released from the station. The radioactivity released from Shippingport Station is far too small to have any measurable effect on the general background environmental radioactivity outside the plant.

  3. SR's reactor tank inspection program: UT development, application, and results

    SciTech Connect

    Howard, B. ); McKaig, M.M. )

    1990-01-01

    Savannah River Site (SRS) has the nation's only plutonium and tritium production reactors. All three reactors have been idle for more than a year so that a variety of modifications can be made. Modifications are being carried out to enhance safety and technical systems. A 1987 decision was made to develop an inspection capability which would allow volumetric inspection of the SRS reactor tanks for the purpose of life extension. The scope of this inspection was defined to address the heat affected zones (HAZ's) of the tanks' weldments for the presence of service induced flaws, i.e., intergranular stress corrosion cracking (IGSCC). In order to be consistent with the existing practices and technology of the nuclear industry a state-of-the-art ultrasonic (UT) examination was chosen as the primary examination medium. Both ultrasonic and eddy current testing were selected as complementary methods for this application, since both can be configured to acquire test data remotely, and the test data can be digitized and stored for post-test analysis. Since intergranular stress corrosion cracking was believed to be the service-induced flaw most likely to occur adjacent to SRS's type 304 stainless steel reactor tank welds, the Savannah River Site's nondestructive testing specialists were faced with a unique challenge. Up to this point the major concentration of effort in the commercial nuclear world has been to apply ultrasonic testing techniques which were developed to detect and size IGSCC on the inside surface of piping with the search unit scanning on the outside surface of the pipe. Proven methods for detection and depth sizing IGSCC which initiated on the near surface (the surface in which the ultrasonic wave enters the metal) had not been established.

  4. SP-100 reactor diassembly remote handling test program

    NASA Astrophysics Data System (ADS)

    Wilson, Charles E.; Potter, Jerry D.; Maiden, Glenn E.; Vader, David P.

    This paper is presented as an overview of the remote handling equipment validation testing, which will be conducted before installation and use in the ground engineeering test facility. This equipment will be used to defuel the SP-100 reactor core after removing it from the Test Assembly following nuclear testing. A series of full scale mock-up operational tests will be conducted at a Hanford Site facility to verify equipment design, operation, and capabilities.

  5. Materials technology for an advanced space power nuclear reactor concept: Program summary

    NASA Technical Reports Server (NTRS)

    Gluyas, R. E.; Watson, G. K.

    1975-01-01

    The results of a materials technology program for a long-life (50,000 hr), high-temperature (950 C coolant outlet), lithium-cooled, nuclear space power reactor concept are reviewed and discussed. Fabrication methods and compatibility and property data were developed for candidate materials for fuel pins and, to a lesser extent, for potential control systems, reflectors, reactor vessel and piping, and other reactor structural materials. The effects of selected materials variables on fuel pin irradiation performance were determined. The most promising materials for fuel pins were found to be 85 percent dense uranium mononitride (UN) fuel clad with tungsten-lined T-111 (Ta-8W-2Hf).

  6. Quarterly Progress Report - Biological Monitoring Program for East Fork Poplar Creek

    SciTech Connect

    Adams, S.M.; Christensen, S.W.; Greeley, M.S. jr; Hill, W.R.; McCarthy, J.F.; Peterson, M.J.; Ryon, M.G.; Smith, J.G.; Southworth, G.R.; Stewart, A.J.

    2000-07-18

    In May 1985, a National Pollutant Discharge Elimination System (NPDES) permit was issued for the Oak Ridge Y-12 Plant. As a condition of the permit, a Biological Monitoring and Abatement Program (BMAP) was developed to demonstrate that the effluent limitations established for the Y-12 Plant protect the classified uses of the receiving stream (East Fork Poplar Creek; EFPC), in particular, the growth and propagation of aquatic life (Loar et al. 1989). A second objective of the BMAP is to document the ecological effects resulting from the implementation of a water pollution control program designed to eliminate direct discharges of wastewaters to EFPC and to minimize the inadvertent release of pollutants to the environment. Because of the complex nature of the discharges to EFPC and the temporal and spatial variability in the composition of the discharges, a comprehensive, integrated approach to biological monitoring was developed. A new permit was issued to the Y-12 Plant on April 28, 1995 and became effective on July 1, 1995. Biological monitoring continues to be required under the new permit. The BMAP consists of four major tasks that reflect different but complementary approaches to evaluating the effects of the Y-12 Plant discharges on the aquatic integrity of EFPC. These tasks are (1) toxicity monitoring, (2) biological indicator studies, (3) bioaccumulation studies, and (4) ecological surveys of the periphyton, benthic macroinvertebrate, and fish communities. Monitoring is currently being conducted at five primary EFPC sites, although sites may be excluded or added depending upon the specific objectives of the various tasks. Criteria used in selecting the sites include: (1) location of sampling sites used in other studies, (2) known or suspected sources of downstream impacts, (3) proximity to U.S. Department of Energy (DOE) Oak Ridge Reservation (ORR) boundaries, (4) concentration of mercury in the adjacent floodplain, (5) appropriate habitat distribution, and

  7. Quarterly Progress Report - Biological Monitoring Program for East Fork Poplar Creek

    SciTech Connect

    Adams, S.M.; Christensen, S.W.; Greeley, M.S.jr; Hill, W.R.; McCarthy, J.F.; Peterson, M.J.; Ryon, M.G.; Smith, J.G.; Southworth, G.R.; Stewart, A.J.

    2000-10-18

    In May 1985, a National Pollutant Discharge Elimination System (NPDES) permit was issued for the Oak Ridge Y-12 Plant. As a condition of the permit, a Biological Monitoring and Abatement Program (BMAP) was developed to demonstrate that the effluent limitations established for the Y-12 Plant protect the classified uses of the receiving stream (East Fork Poplar Creek; EFPC), in particular, the growth and propagation of aquatic life (Loar et al. 1989). A second objective of the BMAP is to document the ecological effects resulting from the implementation of a water pollution control program designed to eliminate direct discharges of wastewaters to EFPC and to minimize the inadvertent release of pollutants to the environment. Because of the complex nature of the discharges to EFPC and the temporal and spatial variability in the composition of the discharges, a comprehensive, integrated approach to biological monitoring was developed. A new permit was issued to the Y-12 Plant on April 28, 1995 and became effective on July 1, 1995. Biological monitoring continues to be required under the new permit. The BMAP consists of four major tasks that reflect different but complementary approaches to evaluating the effects of the Y-12 Plant discharges on the aquatic integrity of EFPC. These tasks are (1) toxicity monitoring, (2) biological indicator studies, (3) bioaccumulation studies, and (4) ecological surveys of the periphyton, benthic macroinvertebrate, and fish communities. Monitoring is currently being conducted at five primary EFPC sites, although sites may be excluded or added depending upon the specific objectives of the various tasks. Criteria used in selecting the sites include: (1) location of sampling sites used in other studies, (2) known or suspected sources of downstream impacts, (3) proximity to U.S. Department of Energy (DOE) Oak Ridge Reservation (ORR) boundaries, (4) concentration of mercury in the adjacent floodplain, (5) appropriate habitat distribution, and

  8. Quarterly Progress Report - Biological Monitoring Program for East Fork Poplar Creek

    SciTech Connect

    Adams, S.M.; Christensen, S.W.; Greeley, M.S.jr; Hill, W.R.; McCarthy, J.F.; Peterson, M.J.; Ryon, M.G.; Smith, J.G.; Southworth, G.R.; Stewart, A.J.

    2000-04-18

    In May 1985, a National Pollutant Discharge Elimination System (NPDES) permit was issued for the Oak Ridge Y-12 Plant. As a condition of the permit, a Biological Monitoring and Abatement Program (BMAP) was developed to demonstrate that the effluent limitations established for the Y-12 Plant protect the classified uses of the receiving stream (East Fork Poplar Creek; EFPC), in particular, the growth and propagation of aquatic life (Loar et al. 1989). A second objective of the BMAP is to document the ecological effects resulting from the implementation of a water pollution control program designed to eliminate direct discharges of wastewaters to EFPC and to minimize the inadvertent release of pollutants to the environment. Because of the complex nature of the discharges to EFPC and the temporal and spatial variability in the composition of the discharges, a comprehensive, integrated approach to biological monitoring was developed. A new permit was issued to the Y-12 Plant on April 28, 1995 and became effective on July 1, 1995. Biological monitoring continues to be required under the new permit. The BMAP consists of four major tasks that reflect different but complementary approaches to evaluating the effects of the Y-12 Plant discharges on the aquatic integrity of EFPC. These tasks are (1) toxicity monitoring, (2) biological indicator studies, (3) bioaccumulation studies, and (4) ecological surveys of the periphyton, benthic macroinvertebrate, and fish communities. Monitoring is currently being conducted at five primary EFPC sites, although sites may be excluded or added depending upon the specific objectives of the various tasks. Criteria used in selecting the sites include: (1) location of sampling sites used in other studies, (2) known or suspected sources of downstream impacts, (3) proximity to U.S. Department of Energy (DOE) Oak Ridge Reservation (ORR) boundaries, (4) concentration of mercury in the adjacent floodplain, (5) appropriate habitat distribution, and

  9. U.S. Department of Energy Program of International Technical Cooperation for Research Reactor Utilization

    SciTech Connect

    Chong, D.; Manning, M.; Ellis, R.; Apt, K.; Flaim, S.; Sylvester, K.

    2004-10-03

    The U.S. Department of Energy, National Nuclear Security Administration (DOE/NNSA) has initiated collaborations with the national nuclear authorities of Egypt, Peru, and Romania for the purpose of advancing the commercial potential and utilization of their respective research reactors. Under its Office of International Safeguards ''Sister Laboratory'' program, DOE/NNSA has undertaken numerous technical collaborations over the past decade intended to promote peaceful applications of nuclear technology. Among these has been technical assistance in research reactor applications, such as neutron activation analysis, nuclear analysis, reactor physics, and medical radioisotope production. The current collaborations are intended to provide the subject countries with a methodology for greater commercialization of research reactor products and services. Our primary goal is the transfer of knowledge, both in administrative and technical issues, needed for the establishment of an effective business plan and utilization strategy for the continued operation of the countries' research reactors. Technical consultation, cooperation, and the information transfer provided are related to: identification, evaluation, and assessment of current research reactor capabilities for products and services; identification of opportunities for technical upgrades for new or expanded products and services; advice and consultation on research reactor upgrades and technical modifications; characterization of markets for reactor products and services; identification of competition and estimation of potential for market penetration; integration of technical constraints; estimation of cash flow streams; and case studies.

  10. Peat biogasification development program. Quarterly progress report No. 5, for period October 1 - December 31, 1980

    SciTech Connect

    Wise, Dr., Donald L.

    1981-01-15

    Progress is reported in the peat biogasification development program. The objective of the research is to compile the necessary data for the design and operation of a peat anaerobic digestion process development unit. Five areas are addressed: pretreatment information; anaerobic digestion; evaluation of waste streams; process model development and economic analysis; and planning for the process development unit. During the reporting period extensive data was taken for the development of the predictive process model. A number of batch and continuous pretreatment experiments were completed and analyzed. The four samples being analyzed through solvent extration were completed, and the results are presented. Work on High Pressure Liquid Chromatography continued, and the development of the gradient elution solvent system was completed with encouraging results. Pretreated peat has been batch fermented; the continuously oxidized peat has shown conversions of close to 30%. This is significantly higher than the conversions for the batch oxidized peat. Continuous digesters have been in operation for approximately one month. Development of a predictive process model for the three phases of peat biogasification, solubilization, oxidation, and fermentation, continued with very good results. The models for solubilization and oxidation were developed and experimental data are being gathered for the fermentation phase of the process model. (DMC)

  11. Enhanced oil recovery and applied geoscience research program. [Quarterly] report, April 1--June 30, 1993

    SciTech Connect

    Thomas, C.P.

    1993-12-31

    The objectives of this research program are to develop microbial enhanced oil recovery (MEOR) systems for application to reservoirs containing medium to heavy oils and to evaluate reservoir wettability and its effects on oil recovery. The MEOR research goals include: (a) development of bacterial cultures that are effective for oil displacement under a broad range of reservoir conditions, (b) improved understanding of the mechanisms by which microbial systems displace oil under reservoir conditions, (c) determination of the feasibility of combining microbial systems with or following conventional enhanced oil recovery (EOR) processes, (d) development and implementation of industry cost-shared field demonstration projects for MEOR technology. The goals of the reservoir wettability project are to develop: (a) better methods for assessment of reservoir core wettability, (b) more certainty in relating laboratory core analysis procedures to field conditions, (c) a better understanding of the effects of reservoir matrix properties and heterogeneity on wettability, and (d) improved ability to predict and influence waterflood and EOR response through control of wettability in reservoirs.

  12. Long Term Materials Test Program. Quarterly report, July-September 1983

    SciTech Connect

    Not Available

    1984-04-01

    Corrosion and erosion/corrosion testing of gas turbine vane and blade base alloys and a variety of protective coating systems under the Long Term Materials Test program has surpassed 3400 hours. The PFBC facility at Malta, New York continues to show an exceptionally high degree of reliability and consistency in performance. Operating conditions include a 1650/sup 0/F bed temperature at 10 atmospheres pressures utilizing Pittsburgh No. 8 coal and a low alkali dolomite sulfur sorbent. After 2687 hours, unprotected nickel and cobalt base vane and blade alloys generally experienced corrosion rates of 1 to 2 mils/1000 hours at metal temperatures of 1100, 1300, and 1500/sup 0/F. Precious metal aluminide and MCrAlY coatings continue to show excellent corrosion resistance (<0.5 mils/1000 hrs) at 1500/sup 0/F, but are susceptible to varying degrees of pitting attack at 1100/sup 0/ and 1300/sup 0/F. Erosion/corrosion degradation rates at 800 to 900 fps., 1350/sup 0/F and less than 100 ppM dust loading ranged from 1 to 4 mils/1000 hours with corrosion predominately concentrated in areas of particle impaction indicating an erosion/corrosion synergism.

  13. Jointly sponsored research program. Quarterly technical progress report, April--June, 1994

    SciTech Connect

    Not Available

    1994-10-01

    Objectives, accomplishments, procedures, and results are briefly described for each of the following 18 research projects: Development and demonstration of a practical electric downhole steam generator for thermal recovery of heavy oil and tar; Wetting behavior of selected crude oil/brine/rock systems; Coal gasification, power generation, and product market study; The impact of leachate from Clean Coal Technology waste on the stability of clay liners; Investigation of coprocessing of heavy oil, automobile shredder residue, and coal; Injection into coal seams for simultaneous CO{sub 2} mitigation and enhanced recovery of coalbed methane; Optimization of carbonizer operations in the FMC Coke Process; Chemical sensor and field screening technology development; Demonstration of the Koppelman Series C Process using a batch test unit with Powder River Basin coal as feed; Remote chemical sensor development; Market assessment and technical feasibility study of PFBC ash use; Solid-state NMR analysis and interpretation of naturally and artificially matured kerogens; CROW{trademark} field demonstration with bell lumber and pole; ``B`` series pilot plant tests; In situ treatment of manufactured gas plant contaminated soils demonstration program; Development and demonstration of a wood-fired gas turbine system; NMR analysis of Mowry Formation shale from different sedimentary basins; and Acid-mine drainage prevention, control, and treatment technology development for the Stockett/Sand Coulee Area.

  14. Jointly sponsored research program quarterly technical progress report, January--March 1994

    SciTech Connect

    Not Available

    1994-08-01

    Progress reports are presented for the following tasks: Development and demonstration of a practical electric downhole steam generator for thermal recovery of heavy oil and tar; wetting behavior of selected crude oil/brine/rock systems; coal gasification, power generation, and product market study; impact of leachate from clean coal technology waste on the stability of clay liners; investigation of coprocessing of heavy oil, automobile shredder residue, and coal; injection into coal seams for simultaneous CO{sub 2} mitigation and enhanced recovery of coalbed methane; optimization of carbonizer operations in the FMC coke process; chemical sensor and field screening technology development; demonstration of the Koppelman ``Series C`` Power River Basin coal as feed; remote chemical sensor development; market assessment and technical feasibility study of PFBC ash use; solid-state NMR analysis and interpretation of naturally and artificially matured kerogens; Crow{trademark} field demonstration with Bell Lumber and Pole; ``B`` series pilot plant tests; and in-situ treatment of manufactured gas plant contaminated soils demonstration program.

  15. Safeguards Material Control and Accounting Program. Quarterly report, April-June 1980

    SciTech Connect

    Poggio, A.J.; Dunn, D.R.

    1980-12-01

    This report summarizes the April-June 1980 activities of the Safeguards Material and Accounting Program sponsored by the US Nuclear Regulatory Commission (NRC) at the Lawrence Livermore National Laboratory. Progress is described on the application and further development of computer-based methodologies for assessing the vulnerabilities of MC and A systems in nuclear fuel-cycle facilities. The application effort involved an assessment of a scrap processing facility with the Structured Assessment Approach (SAA) methodology. The development effort concentrated on making the SAA more user-oriented. Work continued in providing technical analyses to assist the NRC in its development of the forthcoming MC and A upgrade rule. The technical analyses have involved value-impact studies on the draft MC and A upgrade rule using the LLNL Aggregrated Systems Model; specifically, progress has been made on the development of five MC and A performance measures. Other work has included the development of four protection principles for protecting MC and A data from falsification. We also describe progress in analyzing the actual and potential value of an NRC interfacility material accounting system for detecting data falsification.

  16. High-magnetic-field MHD-generator program. Quarterly report, January 1, 1981-March 31, 1981

    SciTech Connect

    1981-04-01

    Progress in an experimental and theoretical program designed to investigate MHD channel phenomena which are important at high magnetic fields is reported. The areas of research include nonuniformity effects, boundary layers, Hall field breakdown, the effects of electrode configuration and current concentrations, and studies of steady-state combustion disk and linear channels in an existing 6 Tesla magnet of small dimensions. In the study of the effects of nonuniformities, experiments have been performed to test a multi-channel, fiber optics diagnostic system that yields time-resolved temperature profiles in an MHD channel. For the study of magneto-acoustic fluctuation phenomena, a one-dimensional model has been developed to describe the performance of a non-ideal MHD generator with a generalized electrical configuration. The installation of the hardware for the data acquisition and reduction of the laser Doppler velocimeter data, to be used in the study of turbulence suppression in a magnetic field, has been nearly completed. A two-dimensional MHD computer code has been developed which predicts the dependence on electrode and insulator dimensions of the onset of interelectrode Hall field breakdown. Calculations have been performed of the effects of nonuniformities on the flow and electrical behavior of baseload-sized disk generators.

  17. Nuclear medicine program progress report for quarter ending December 31, 1996

    SciTech Connect

    Knapp, F.F. Jr.; Beets, A.L.; Boll, R.; Luo, H.; McPherson, D.W.; Mirzadeh, S.

    1997-03-20

    In this report the authors describe the use of an effective method for concentration of the rhenium-188 bolus and the results of the first Phase 1 clinical studies for bone pain palliation with rhenium-188 obtained from the tungsten-188/rhenium-188 generator. Initial studies with therapeutic levels of Re-188-HEDP at the Clinic for Nuclear Medicine at the University of Bonn, Germany, have demonstrated the expected good metastatic uptake of Re-188-HEDP in four patients who presented with skeletal metastases from disseminated prostatic cancer with good pain palliation and minimal marrow suppression. In addition, skeletal metastatic targeting of tracer doses of Re-188(V)-DMSA has been evaluated in several patients with metastases from prostatic cancer at the Department of Nuclear Medicine at the Canterbury and Kent Hospital in Canterbury, England. In this report the authors also describe further studies with the E-(R,R)-IQNP ligand developed in the ORNL Nuclear Medicine Program as a potential imaging agent for detection of changes which may occur in the cerebral muscarinic-cholinergic receptors (mAChR) in Alzheimer`s and other diseases.

  18. Commercial Nuclear Waste Research and Development Program. Quarterly report, April-June 1985

    SciTech Connect

    1985-07-01

    Support was provided to DOE/NV during preparation of a proposal, requested by the DOE San Francisco office, for performance of SP-100 Ground Engineering Systems tests at the E-MAD facility. The site selection committee visited the Nevada Test Site in May for a tour and briefings on all aspects of the proposal. The fuel assembly used in the two-year metal cask simulation test was removed from the test stand and characterized to document its post-test condition. Fuel assembly integrity monitoring for the second half of FY 1985 was completed of six of the fuel assemblies being stored in unwelded canisters. Post-storage characterization was completed on three fuel assemblies which were stored in welded canisters. All test procedures have been completed and delivered for the Canister Assembly Launch Test Program being conducted at another Area 25 facility. The "Safety Assessment Document for Spent Fuel Handling, Packaging, and Storage Demonstrations at the E-MAD Facility on the Nevada Test Site," DOE/NV10250-20, was revised to be consistent with new and revised DOE Orders and Directives, and delivered to DOE/NV.

  19. Jointly sponsored research program. Quarterly technical progress report, October--December 1993

    SciTech Connect

    Deans, H.A.

    1994-05-01

    This is a progress report on work performed by Western Research Institute for the U.S. DOE, Morgantown Energy Technology Center in the period October- December 1993. Tasks addressed include: development and demonstration of a practical electric downhole steam generator for thermal recovery of heavy oil and tar; wetting behavior of selected crude oil/brine/rock systems; coal gasification, power generation, and product market study; the impact of leachate from clean coal technology waste on the stability of clay liners; investigation of coprocessing of heavy oil, automobile shredder residue, and coal; injection into coal seams for simultaneous CO{sub 2} mitigation and enhanced recovery of coalbed methane; optimization of carbonizer operations in the FMC coke process; chemical sensor and field screening technology development; demonstration of the koppelman {open_quotes}series c{close_quotes} process using a batch test unit with Powder River Basin coal as feed; remote chemical sensor development; market assessment and technical feasibility study of PFBC ash use; solid-state NMR analysis and interpretation of naturally and artificially matured kerogens; Crow{trademark} field demonstration with bell lumber and pole; {open_quotes}B{close_quotes} series pilot plant tests; in situ treatment of manufactured gas plant contaminated soils demonstration program.

  20. Development of a pilot-scale kinetic extruder feeder system and test program. Second quarterly technical progress report, January-March 1981

    SciTech Connect

    Not Available

    1981-04-15

    This report covers the work carried out during the January-March 1981 quarter of the program. Preparations are being made to ready the equipment for the moisture tolerance test program. The main effort described pertains to the redesign and procurement of the main shaft bearing and seal system. To enhance the chances of achieving the program objectives, the recommendation was made by Lockheed to use a conventional roller bearing for the present program instead of the advanced water-lubricated bearing. Nevertheless, the need exists for better long-term solutions to the bearing and seal problem, especially in view of the eventual requirement to scale the equipment to larger sizes. It is recommended that the program proceed as planned.

  1. Quarterly Progress Report - Biological Monitoring Program for East Fork Poplar Creek

    SciTech Connect

    Adams, S. M.; Christensen, S. W.; Greeley, M.S. jr; McCracken, M.K.; Peterson, M.J.; Ryon, M.G.; Smith, J.G.; Southworth G. R.; Stewart, A. J.

    2001-01-19

    In May 1985, a National Pollutant Discharge Elimination System (NPDES) permit was issued for the Oak Ridge Y-12 National Security Complex (formerly the Oak Ridge Y-12 Plant). As a condition of the permit, a Biological Monitoring and Abatement Program (BMAP) was developed to demonstrate that the effluent limitations established for the Y-12 Complex protect the classified uses of the receiving stream (East Fork Poplar Creek; EFPC), in particular, the growth and propagation of aquatic life (Loar et al. 1989). A second objective of the BMAP is to document the ecological effects resulting from the implementation of a water pollution control program designed to eliminate direct discharges of wastewaters to EFPC and to minimize the inadvertent release of pollutants to the environment. Because of the complex nature of the discharges to EFPC and the temporal and spatial variability in the composition of the discharges, a comprehensive, integrated approach to biological monitoring was developed. A new permit was issued to the Y-12 Complex on April 28, 1995 and became effective on July 1, 1995. Biological monitoring continues to be required under the new permit. The BMAP consists of four major tasks that reflect different but complementary approaches to evaluating the effects of the Y-12 Complex discharges on the aquatic integrity of EFPC. These tasks are (1) toxicity monitoring, (2) biological indicator studies, (3) bioaccumulation studies, and (4) ecological surveys of the periphyton, benthic macroinvertebrate, and fish communities. Monitoring is currently being conducted at five primary EFPC sites, although sites may be excluded or added depending upon the specific objectives of the various tasks. Criteria used in selecting the sites include: (1) location of sampling sites used in other studies, (2) known or suspected sources of downstream impacts, (3) proximity to U.S. Department of Energy (DOE) Oak Ridge Reservation (ORR) boundaries, (4) concentration of mercury in the

  2. Nuclear Medicine Program progress report for quarter ending September 30, 1989

    SciTech Connect

    Knapp, F.F. Jr.; Ambrose, K.R.; Callahan, A.P.; Allred, J.F.; Blystone, S.L.; Hasan, A.; McPherson, D.W.; Srivastava, P.C.; Lambert, C.R.; Lambert, S.J.; Rice, D.E.

    1989-12-01

    In this report, an evaluation of the effects of albumin and albumin plus sodium palmitate in the phosphate buffer perfusate on the relative of unmetabolized fatty acid and the unknown metabolite(s) from isolated rat hearts administered 15-(p-(I-125)iodophenyl)-3-(R, S)-methylpentadecanoic acid (BMIPP) is described. Earlier studies had demonstrated the presence of a major unidentified polar radioactive component in the outflow of hearts injected with BMIPP and perfused with the traditional Krebs-Henseleit (KH) buffer, which does not contain albumin. The current studies were performed with KH buffer containing either albumin (BSA) or albumin and palmitate (BSA/PAL) to assess the relative loss of the metabolite and unmetabolized BMIPP from the perfused hearts. The results demonstrated that in the presence of albumin both the unidentified material and BMIPP are present in the outflow (i.e., 5 min perfusate buffer, % BMIPP: KH, 3%; KH + BSA, 10%; KH + BSA/PAL, 41%). These results demonstrate that BMIPP is a major radioactive component in the outflow of isolated hearts using a perfusate containing BSA and palmitate and, more importantly, suggest for the first time that the slow myocardial wash-out observed in humans after administration of (I-123)BMIPP probably represents loss of both unmetabolized BMIPP and the unidentified metabolite. Coronary sinus sampling studies with dogs are now in progress to relate the relative contribution of these two components to the release of radioactivity from the heart. Also in this report, our population experience for several radioisotopes being used by the ORNL Nuclear Medicine Program is summarized.

  3. Chemical Engineering Division fuel cycle programs. Quarterly progress report, July-September 1978

    SciTech Connect

    Steindler, M.J.; Ader, M.; Barletta, R.E.

    1980-01-01

    Fuel cycle work included hydraulic performance and extraction efficiency of eight-stage centrifugal contactors, flowsheet for the Aralex process, Ru and Zr extraction in a miniature centrifugal contactor, study of Zr aging in the organic phase and its effect on Zr extraction and hydraulic testing of the 9-cm-ID contactor. Work for predicting accident consequences in LWR fuel processing covered the relation between energy input (to subdivide a solid) and the modes of particle size frequency distribution. In the pyrochemical and dry processing program corrosion-testing materials for containment vessels and equipment for studying carbide reactions in bismuth is under way. Analytical studies have been made of salt-transport processes; efforts to spin tungsten crucibles 13 cm dia continue, and other information on tungsten fabrication is being assembled; the process steps of the chloride volatility process have been demonstrated and the thoria powder product used to produce oxide pellets; solubility of UO/sub 2/, PuO/sub 2/, and fission products in molten alkali nitrates is being investigated; work was continued on reprocessing actinide oxides by extracting the actinides into ammonium chloroaluminate from bismuth; the preparation of thorium-uranium carbide from the oxide is being studied as a means of improving the oxide reactivity; studies are in progress on producing uranium metal and decontaminated ThO/sub 2/ by the reaction of (Th,U)O/sub 2/ solid solution in molten salts containing ThCl/sub 4/ and thorium metal chips. In the molten tin process, no basic thermodynamic or kinetic factors have been found that may limit process development.

  4. Chemical Engineering Division fuel cycle programs. Quarterly progress report, October-December 1978

    SciTech Connect

    Steindler, M J; Ader, M; Barletta, R E

    1980-01-01

    In the program on pyrochemical and dry processing methods (PDPM) for nuclear fuel, tungsten crucibles were successfully spun for use in laboratory-scale experiments. Corrosion testing of refractory metals and alloys in PDPM environments was done. Ceramic substrates were successfully coated with tungsten. Solubility measurements were made to determine Cd/Mg alloy composition and temperature at which dissolved Th will precipitate. Experiments were started to study the reduction of high-fired ThO/sub 2/ with Ca in a molten metal-molten salt system. Work on the fused salt electrolysis of CaO was started. Equipment for determining phase diagrams for U-Cu-Mg system was set up. The reaction of UO/sub 2/ with molten equimolar NaNO/sub 3/-KNO/sub 3/ was studied as part of a project to identify chemically feasible nonaqueous fuel reprocessing methods. Work was continued on development of a flowsheet for reprocessing actinide oxides by extracting actinides into ammonium chloro-aluminate (and alternative salts) from a bismuth solution. Preparation of Th, U, and Pu nitrides after dissolution of spent fuel elements in molten tin is being studied. Leach rates of glass beads, pulverized beads, and beads encapsulated in a lead matrix with no protective envelope were studied. A method (employing no pressure or vacuum systems) of encapsulating various solid wastes in a lead metal matrix was developed and tested. A preliminary integration was made of earlier data on effects of impacts on metal-matrix waste forms.Leach migration experiments were compared with conventional infiltration experiments as methods of evaluating geologic formations as barriers to nuclide migration. The effect of the streaming potential on the rates of transport of radioactive I/sup -/ and Na/sup +/ through kaolinite columns was measured, as well as adsorption of iodide and iodate by several compounds; implications of the results upon the disposal of radioactive iodine are discussed.

  5. Nuclear medicine program progress report for quarter ending March 31, 1994

    SciTech Connect

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Lambert, C.R.; McPherson, D.W.; Mirzadeh, S.; Luo, H.

    1994-05-01

    The authors` new radioiodinated ``IQNP`` agent, an analogue of ``4-IQNB``, has a high affinity for the muscarinic-cholinergic receptor (m-AChR). Iodine is stabilized in ``IQNP`` by attachment as a vinyl iodide. To evaluate the potential usefulness of a [Br-76]-labeled analogue as a candidate for positron emission tomography (PET), they have synthesized the trans-3-bromopropenyl analogue (BrQNP) and evaluated its ability in vivo to block uptake of [I-125]-Z-(R,R)-IQNP. Reaction of bromine with the trans-tributylstannyl substrate prepared from ethyl -{alpha}-hydroxy -{alpha}-phenyl-{alpha}-(1-propyn-3-yl)acetate, followed by column purification and transesterification with (R,S)-3-quinuclidinol gave BrQNP. Female rats were pre-treated with the oxalate salt of BrQNP one hour prior to I.V. injection of [I-125]-IQNP. While the brain and heart uptake in BrQNP pre-treated animals was significantly decreased, the control animals showed the expected high uptake of IQNP in these tissues. The ease of preparation and ability to block m-AChR suggest that [Br-76]-labeled BrQNP is a potential candidate for PET studies. In this report, the authors also summarize their current on-going collaborative studies assessing the usefulness of various rhenium-188-labeled therapeutic agents. In addition, collaborative programs have been established to evaluate rhenium-188-labeled particles for treatment of arthritis (synovectomy), treatment of bone pain resulting from cancer metastheses with rhenium-188-phosphonates (palliation), and other applications.

  6. University Reactor Instrumentation grant program. Final report, September 7, 1990--August 31, 1995

    SciTech Connect

    Talnagi, J.W.

    1998-06-17

    The Ohio State University Nuclear Reactor Laboratory (OSU NRL) participated in the Department of Energy (DOE) grant program commonly denoted as the University Reactor Instrumentation (URI) program from the period September 1990 through August 1995, after which funding was terminated on a programmatic basis by DOE. This program provided funding support for acquisition of capital equipment targeted for facility upgrades and improvements, including modernizing reactor systems and instrumentation, improvements in research and instructional capabilities, and infrastructure enhancements. The staff of the OSU NRL submitted five grant applications during this period, all of which were funded either partially or in their entirety. This report will provide an overview of the activities carried out under these grants and assess their impact on the OSU NRL facilities.

  7. Unocal Parachute Creek Shale Oil Program. Environmental Monitoring Plan, Quarterly report. Second quarter 1989. Report for 1 April-30 June 1989

    SciTech Connect

    Not Available

    1989-08-31

    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 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 and the rationale for Tier I and Tier II monitoring are explained in the Environmental Monitoring Plan.

  8. (Shippingport Atomic Power Station). Quarterly operating report, fourth quarter 1980

    SciTech Connect

    Not Available

    1980-01-01

    At the beginning of the fourth quarter of 1980, the Shippingport Atomic Power Station remained shutdown for the normally planned semiannual maintenance and testing program, initiated September 12, 1980. Operational testing began on November 7. Maximum power was achieved November 28 and was maintained throughout the remainder of the quarter except as noted. The LWBR Core has generated 19,046.07 EFPH from start-up through the end of the quarter. During this quarter, approximately 0.000025 curies of Xe 133 activity were released from the station. During the fourth quarter of 1980, 1081 cubic feet of radioactive solid waste was shipped out of state for burial. These shipments contained 0.037 curies of radioactivity.

  9. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report October 1 - December 31, 2004

    SciTech Connect

    Sisterson, DL

    2004-12-31

    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 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 annual OPSMAX time for the Southern Great Plains (SGP) site is 8,322 hours per year (0.95 × 8,760, the number hours in a year, not including leap year). The annual OPSMAX for the North Slope Alaska (NSA) site is 7,884 hours per year (0.90 × 8,760), and that for the Tropical Western Pacific (TWP) site is 7,446 hours per year (0.85 × 8,760). 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

  10. Nuclear Medicine Program progress report for quarter ending June 30, 1993

    SciTech Connect

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Callahan, A.P.; Hsieh, B.T.; McPherson, D.W.; Mirzadeh, S.; Lambert, C.R.

    1993-07-01

    The ``IQNP`` agent is an antagonist for the cholinergic-muscarinic receptor. Since the IQNP molecule has two asymmetric centers and either cis or trans isomerism of the vinyl iodide, there are eight possible isomeric combinations. In this report, the systematic synthesis, purification and animal testing of several isomers of radioiodinated ``IQNP`` are reported. A dramatic and unexpected relation between the absolute configuration at the two asymmetric centers and the stereochemistry of the vinyl iodide on receptor specificity was observed. The E-(R)(R) isomer shows specific and significant localization (per cent dose/gram at 6 hours) in receptor-rich cerebral structures (i.e. Cortex = 1.38 + 0.31; Striatum = 1.22 + 0.20) and low uptake in tissues rich in the M{sub 2} subtype (Heart = 0.10; Cerebellum = 0.04). In contrast, the E-(R)(S) isomer shows very low receptor-specific uptake (Cortex = 0.04; Striatum = 0.02), demonstrating the importance of absolute configuration at the acetate center. An unexpected and important observation is that the stereochemistry of the vinyl iodine appears to affect receptor subtype specificity, since the Z-(R,S)(R) isomer shows much higher uptake in the heart (0.56 + 0.12) and cerebellum (0.17 + 0.04). Studies are now in progress to confirm these exciting results in vitro. Progress has also continued during this period with several collaborative programs. The first large-scale clinical tungsten-188/rhenium-188 generator prototype (500 mCi) was fabricated and supplied to the Center for Molecular Medicine and Immunology (CMMI), in Newark, New Jersey, for Phase I clinical trials of rhenium-188-labeled anti CEA antibodies for patient treatment. Collaborative studies are also continuing in conjunction with the Nuclear Medicine Department at the University of Massachusetts where a generator is in use to compare the biological properties of {open_quotes}direct{close_quotes} and {open_quotes}indirect{close_quotes} labeled antibodies.

  11. Chemical Engineering Division Fuel Cycle Programs. Quarterly progress report, January-March 1979

    SciTech Connect

    Steindler, M J; Ader, M; Barletta, R E

    1980-01-01

    In the program on pyrochemical and dry processing methods (PDPM) for nuclear fuel, corrosion testing of refractory metals and alloys, graphite, and SiC in PDPM environments was done. A tungsten-metallized Al/sub 2/O/sub 3/-3% Y/sub 2/O/sub 3/ crucible was successfully fabricated. Tungsten microstructure of a plasma-sprayed tungsten crucible was stabilized by nickel infiltration and heat treatment. Solubility measurements of Th in Cd and Cd-Mg alloys were continued, as were experiments to study the reduction of high-fired ThO/sub 2/. Work on the fused salt electrolysis of CaO also was continued. The method of coprocessing of U and Pu by a salt transport process was modified. Tungsten-coated molybdenum crucibles were fabricated. The proliferation resistance of chloride volatility processing of thorium-based fuels is being evaluated by studying the behavior of fission product elements during chlorination of U and Th. Thermodynamic analysis of the phase relationships in the U-Pu-Zn system was initiated. The Pyro-Civex reprocessing method is being reviewed. Reactivity of UO/sub 2/ and PuO/sub 2/ with molten equimolar NaNO/sub 3/-KNO/sub 3/ is being studied along with the behavior of selected fission product elements. Work was continued on the reprocessing of actinide oxides by extracting the actinides from a bismuth solution. Rate of dissolution of UO/sub 2/ microspheres in LiCl/AlCl/sub 3/ was measured. Nitriding rates of Th and U dissolved in molten tin were measured. In work on the encapsulation of radioactive waste in metal, leach rates of a simulated waste glass were studied. Rates of dissolution of metals (potential barrier materials) in aqueous media are being studied. In work on the transport properties of nuclear waste in geologic media, the adsorption of iodate by hematite as a function of pH and iodate concentration was measured. The migration behavior of cesium in limestone was studied in relation to the cesium concentration and pH of simulated groundwater

  12. FFTF and Advanced Reactors Transition Program Resource Loaded Schedule

    SciTech Connect

    GANTT, D.A.

    2000-10-31

    This Resource Load Schedule (RLS) addresses two missions. The Advanced Reactors Transition (ART) mission, funded by DOE-EM, is to transition assigned, surplus facilities to a safe and compliant, low-cost, stable, deactivated condition (requiring minimal surveillance and maintenance) pending eventual reuse or D&D. Facilities to be transitioned include the 309 Building Plutonium Recycle Test Reactor (PRTR) and Nuclear Energy Legacy facilities. This mission is funded through the Environmental Management (EM) Project Baseline Summary (PBS) RL-TP11, ''Advanced Reactors Transition.'' The second mission, the Fast Flux Test Facility (FFTF) Project, is funded through budget requests submitted to the Office of Nuclear Energy, Science and Technology (DOE-NE). The FFTF Project mission is maintaining the FFTF, the Fuels and Materials Examination Facility (FMEF), and affiliated 400 Area buildings in a safe and compliant standby condition. This mission is to preserve the condition of the plant hardware, software, and personnel in a manner not to preclude a plant restart. This revision of the Resource Loaded Schedule (RLS) is based upon the technical scope in the latest revision of the following project and management plans: Fast Flux Test Facility Standby Plan (Reference 1); Hanford Site Sodium Management Plan (Reference 2); and 309 Building Transition Plan (Reference 4). The technical scope, cost, and schedule baseline is also in agreement with the concurrent revision to the ART Fiscal Year (FY) 2001 Multi-Year Work Plan (MYWP), which is available in an electronic version (only) on the Hanford Local Area Network, within the ''Hanford Data Integrator (HANDI)'' application.

  13. A low energy continuous reactor separator for the production of ethanol from corn grits/starch and biomass streams. 3rd Quarterly report, October 15, 1994--January 15, 1995

    SciTech Connect

    Not Available

    1995-02-01

    This project is an attempt to develop and demonstrate an improved reactor for the production of ethanol from starch and ligno-cellulosic streams. Bio-Process Innovations holds a patent of this reactor technology, and is directing the project. A Continuous Stirred Reactor Separator (CSRS) is being built on a pilot plant scale for testing at a small Iowa ethanol plant (Permeate Refining) while bench scale tests on the reactor system are being performed at Purdue University. The project involves two industrial partners, Permeate Refining of Hopkinton, IA who will site and operate the pilot scale unit, and Lamont Sign Co, who are building the pilot scale unit. The CSRS is expected to allow the continuous conversion of various substrates to ethanol. The CSRS unit combines several operations within the confines of the reactor vessel; (1) complex carbohydrates are reduced to simple sugars by enzymatic breakdown; (2) sugars are converted to ethanol by yeast or bacteria; and (3) the ethanol is separated by a stripping gas stream. The ethanol is removed from the stripping gas in an absorber, and then taken to an extractive distillation column. This unit should allow concentrated feeds to be converted to ethanol, and the use of bottoms recycle will be extensively tested to establish the limits of minimizing net bottoms water production leaving the plant. Progress during this quarter is described.

  14. Progress of the RERTR (Reduced Enrichment Research and Test Reactor) Program in 1989

    SciTech Connect

    Travelli, A.

    1989-01-01

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. After a brief summary of the results which the RERTR Program, in collaboration with its many international partners, had achieved by the end of 1988, the major events, findings, and activities of 1989 are reviewed. The scope of the RERTR Program activities was curtailed, in 1989, by an unexpected legislative restriction which limited the ability of the Arms Control and Disarmament Agency to adequately fund the program. Nevertheless, the thrust of the major planned program activities was maintained, and meaningful results were obtained in several areas of great significance for future work. 15 refs., 12 figs.

  15. Computer Program for Solving Nine-Group Diffusion Equations for Cylindrical Reactors

    NASA Technical Reports Server (NTRS)

    Miser, James W.; Hyland, Robert E.; Fieno, Daniel

    1959-01-01

    A method is presented for determining the critical size of a cylindrical reactor by a one-dimensional group-diffusion method extended to a two-dimensional solution by prescribing values of axial leakage based on assumed flux levels. The neutron energy spectrum is divided into nine groups, and the reactor into four concentric cylinders. A computing machine program for an IBM 650 computer with attachments and a method for using the program with nine, or less, groups and four, or less, regions are given.

  16. Review of Savannah River Site K Reactor inservice inspection and testing restart program

    SciTech Connect

    Anderson, M.T.; Hartley, R.S.; Kido, C.

    1992-09-01

    Inservice inspection (ISI) and inservice testing (IST) programs are used at commercial nuclear power plants to monitor the pressure boundary integrity and operability of components in important safety-related systems. The Department of Energy (DOE) - Office of Defense Programs (DP) operates a Category A (> 20 MW thermal) production reactor at the Savannah River Site (SRS). This report represents an evaluation of the ISI and IST practices proposed for restart of SRS K Reactor as compared, where applicable, to current ISI/IST activities of commercial nuclear power facilities.

  17. Geothermal direct-heat utilization assistance. Federal Assistance Program, Quarterly project progress report, October--December 1994

    SciTech Connect

    Not Available

    1994-12-31

    The report summarizes activities of the Geo-Heat Center (GHC) at Oregon Institute of Technology for the first quarter of Fiscal Year 1995. It describes contacts with parties during this period related to assistance with geothermal direct heat projects. Areas dealt with include geothermal heat pumps, space heating, greenhouses, aquaculture, resources and equipment. Research is also being conducted on geothermal energy cost evaluation, low-temperature geothermal resource assessment, use of silica waste from the Cerro Prieto geothermal field as construction materials and geothermal heat pumps. Outreach activities include the publication of a quarterly Bulletin on direct heat applications and dissemination of information on low-temperature geothermal resources and utilization.

  18. Optimization of reactor configuration in coal liquefaction

    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.

  19. Unocal Parachute Creek Shale Oil Program. Environmental Monitoring Plan quarterly report, first quarter, 1989. Report for 1 January 1989-31 March 1989

    SciTech Connect

    Not Available

    1989-05-31

    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. Phase I of the project is to produce 10,000 barrels per day of syncrude from oil shale, using the Unishale 'B' process. The compliance monitoring data, supplemental, environmental, and industrial-hygiene activities are summarized, and the results of the compliance program audit are also included. The main text is 23 pages; the ambient air monitoring reports, including computer data sheets, comprises the bulk of the report.

  20. Unocal Parachute Creek shale-oil Program. Environmental Monitoring Plan quarterly report, fourth quarter, 1988. Report for 1 October-31 December 1988

    SciTech Connect

    Not Available

    1989-02-28

    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 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 the project is to produce 10,000 barrels per day of syncrude from oil shale, using the Unishale 'B' process. The report contains results of industrial hygiene monitoring, a summary of supplemental sampling activities, and copies of compliance-monitoring reports. Details of an independent audit of the compliance programs are provided also. Approximately 30 pages of text and 519 pages of data sheets or reports are included.