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Sample records for operations quarterly technical

  1. Quarterly Performance/Technical Report

    National Research Council Canada - National Science Library

    Coppo, Patricia A

    2006-01-01

    ... a nationwide contingency response plan. 2. Rapid Identification of Matched Donors : Increase operational efficiencies that accelerate the search process and increase patient access are key to preparedness in a contingency event. 3...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-01-01

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

  6. Yucca Mountain Site Characterization Project: Technical Data Catalog quarterly supplement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-03-31

    The March 21, 1993, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the Catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated September 30, 1993, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1994.

  7. Yucca Mountain Site Characterization Project Technical Data Catalog (quarterly supplement)

    International Nuclear Information System (INIS)

    1993-01-01

    The June 1, 1985, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the Catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated December 31, 1992, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1993

  8. Yucca Mountain Site Characterization Project technical data catalog: Quarterly supplement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    The Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where the data may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed-in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and distributed in the month following the end of each quarter. A complete revision to the catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated September 30, 1994, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1995.

  9. Quarterly Technical Progress Report June 2015

    Energy Technology Data Exchange (ETDEWEB)

    Buchholz, Bruce A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-06-08

    The project has two main goals: 1) Identify the types of adducts naphthalene (NA) forms with DNA and 2) determine whether adduct formation correlates with site selective tumor formation in defined subcompartments of the respiratory tract (respiratory and olfactory nasal epithelium and airways of mice, rats and rhesus monkeys). Five tasks are associated with the completion of the goals. Task 1: Contracting and Animal Use Approvals. IACUC and ACURO approvals are complete, The subcontract with UC Davis (UCD) was executed in December 2014. Task 2: Perform In Vitro Study for Goal 1. Rat samples exposed and in freezer while adduct standards are being made. Mouse samples need to be exposed in next quarter. Task 3: Perform In Vitro Study for Goal 2. Mouse ex vivo samples completed. Rat and monkey samples need to be completed in the next quarter. Task 4: Sample Preparation and Analysis. Mouse Goal 2 samples completed. Other samples remain to be done. Task 5: Data Interpretation and Reporting. Need rat data to write paper on adduct formation.

  10. Shippingport Atomic Power Station. Quarterly operating report, third quarter 1978

    Energy Technology Data Exchange (ETDEWEB)

    Jones, T. D.

    1978-01-01

    A loss of ac power to the station occurred on July 28, 1978 caused by an interaction between Beaver Valley Power Station and Shippingport Atomic Power Station when the main transformer of Unit No. 1 of the Beaver Valley Power Station developed an internal failure and tripped the BVPS. Two environmental studies were continued this quarter. The first involves reduction of main unit condenser chlorination and the second, river intake screen fish impingement sampling. There were no radioactive liquid discharges from the Radioactive Waste Processing System to the river this quarter. During the third quarter of 1978, 874 cubic feet of radioactive solid waste was shipped out of state for burial. At the end of the quarter, the Fall shutdown continued with the plant heated up, the main turbine on turning gear and plant testing in progress prior to Station startup.

  11. Operation of Finnish nuclear power plants. Quarterly report, 2nd quarter 1999

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1999-12-01

    Quarterly reports on the operation of Finnish NPPs describe events and observations relating to nuclear and radiation safety that the Finnish Radiation and Nuclear Safety Authority (STUK) considers safety significant. Safety improvements at the plants are also described. The report includes a summary of the radiation safety of plant personnel and the environment and tabulated data on the plants' production and load factors. All Finnish NPP units were in power operation for the whole second quarter of 1999, with the exception of the annual maintenance outages of the Olkiluoto plant units. The load factor average of the plant units in this quarter was 93.1%. Two events in this quarter were classified Level 1 on the INKS Scale. At Olkiluoto 1, a valve of the containment gas treatment system had been in an incorrect position for almost a month, owing to which the system would not have been available as planned in an accident. At Olkiluoto 2, main circulation pump work was done during the annual maintenance outage and a containment personnel air lock was briefly open in violation of the Technical Specifications. Water leaking out of the reactor in an accident could not have been directed to the emergency cooling system because it would have leaked out from the containment via the open personnel air lock. Other events in this quarter had no bearing on the nuclear or radiation safety of the plant units. The individual doses of NPP personnel and also radioactive releases off-site were well below authorised limits. Radioactive substances were measurable in samples collected around the plants in such quantities only as have no bearing on the radiation exposure of the population. (orig.)

  12. RTO Technical Publications: A Quarterly Listing

    Science.gov (United States)

    2002-01-01

    This is a listing of recent unclassified RTO technical publications processed by the NASA Center for AeroSpace Information from Jan 1, 2002 through Mar 31, 2002. Topics covered included information management, ice accretion, digital flight control systems, supercavitation flows, and tactical decision aids.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-12-31

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

  14. (Shippingport Atomic Power Station). Quarterly operating report, third quarter 1979

    Energy Technology Data Exchange (ETDEWEB)

    Jones, T. D.

    1979-01-01

    At the beginning of the third quarter of 1979, the Shippingport Atomic Power Station remained shutdown to complete repairs of the turbine generator hydrogen circulation fan following discovery of a rubbing noise on May 24, 1979. The Station was in a cooldown condition at approximately 180/sup 0/F and 300 psig with a steam bubble in the pressurizer and the reactor coolant pumps in slow speed. The reactor plant cooldown heat exchanger was in service to maintain coolant temperature. The 1A, 1B, 1C, and 1D reactor coolant loops and the 1AC and 1BD purification loops remained in service. All expended PWR Core 2 fuel elements have previously been shipped off-site. The remaining irradiated PWR Core 2 core barrel and miscellaneous refueling tools were in storage under shielding water in the deep pit of the Fuel Handling Building. The LWBR Core has generated 12,111.00 EFPH from startup through the end of the quarter.

  15. Los Alamos National Laboratory Environmental Restoration Project quarterly technical report, April--June 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-08-18

    This quarterly report describes the technical status of activities in the Los Alamos National Laboratory Environmental Restoration (ER) Project. Each activity is identified by an activity data sheet number, a brief title describing the activity or the technical area where the activity is located, and the name of the project leader. The Hazardous and Solid Waste Amendments (HSWA) portion of the facility operating permit requires the submission of a technical progress report on a quarterly basis. This report, submitted to fulfill the permit`s requirement, summarizes the work performed and the results of sampling and analysis in the ER Project. Suspect waste found include: Radionuclides, high explosives, metals, solvents and organics. The data provided in this report have not been validated. These data are considered ``reviewed data.``

  16. Effects of 60 Hz electric fields on operant and social stress behavior of nonhuman primates. Quarterly technical progress report No. 20, September 28-December 20, 1985

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, W.R.

    1986-01-03

    This research program will evaluate the aversive character of exposure to 60 Hz electric fields by determining the threshold intensity which produces avoidance or escape responses, will estimate the threshold intensity for detection of 60 Hz electric fields, will assess effects of chronic exposure to 60 Hz electric fields on the performance of two operant conditioning tasks, fixed ratio and differential reinforcement of low rate responding, will investigate, using the systematic quantitative observational sampling methods of primatology, the possible stress-inducing effects of chronic exposure to 60 Hz electric fields on the behavior of baboons living in small social groups. In all experiments, the electric fields will be described, characterized, and controlled to account for recognized artifacts associated with high intensity 60 Hz electric fields and the health of all subjects will be described using the methods of primate veterinary medicine.

  17. Environmental and economic assessment of discharges from Gulf of Mexico Region oil and gas operation. Quarterly technical progress report, 1 October--31 December 1994

    International Nuclear Information System (INIS)

    Gettleson, D.A.

    1995-01-01

    Task 3 (Environmental Field Sampling and Analysis of NORM, Heavy Metals, and Organics) work included analyses of samples. Task 4 (Monitoring of the Recovery of Impacted Wetland and Open Bay Produced Water Discharge Sites in Coastal Louisiana and Texas) activities involved the continued analyses of samples and field sampling at Bay de Chene. Task 5 (Assessment of Economic Impacts of Offshore and Coastal Discharge Requirements on Present and Future Operations in the Gulf of Mexico Region) activities included preparing a draft final report. Task 6 (Synthesis of Gulf of Mexico Seafood Consumption and Use Patterns) work also involved preparing a draft final report. Task 7 (Technology Transfer Plan) activities included a presentation at the Minerals Management Service Information Transfer Meeting for the Gulf of Mexico OCS Region. Task 8 (Project Management and Deliverables) activities involved the submission of the necessary reports and routine management

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

    International Nuclear Information System (INIS)

    1994-01-01

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

  19. Operation of Finnish nuclear power plants. Quarterly report, 2nd quarter 1996

    International Nuclear Information System (INIS)

    Sillanpaeae, T.

    1996-11-01

    Quarterly Reports on the operation of Finnish nuclear power plants describe events and observations relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety (STUK) considers safety significant. Safety improvements at the plants are also described. The report also includes a summary of the radiation safety of plant personnel and of the environment and tabulated data on the plants' production and load factors. In the second quarter of 1996, the Finnish nuclear power plant units were in power operation except for the annual maintenance outages of TVO plant units and the Midsummer shutdown at TVO II which was due to low electricity demand, a turbine generator inspection and repairs. The load factor average of all plant units was 88.9 %. Events in the second quarter of 1996 were classified level 0 on the International Nuclear Event Scale (INES)

  20. Power systems development facility. Quarterly technical progress report, January 1, 1994--March 31, 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This quarterly technical progress report summarizes work completed during the last quarter of the Second Budget Period, January 1 through March 31, 1994, entitled {open_quotes}Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion.{close_quotes} The objective of this project is to evaluate hot gas particulate control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size.

  1. Operation of Finnish nuclear power plants. Quarterly report, 2nd quarter 1997

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1997-12-01

    Quarterly Reports on the operation of Finnish nuclear power plants describe events and observations relating to nuclear and radiation safety which STUK - Radiation and Nuclear Safety Authority considers safety significant. Safety improvements at the plants are also described. The Report also includes a summary of the radiation safety of plant personnel and of the environment and tabulated data on the plants' production and load factors. The Finnish nuclear power plant units were in power operation in the second quarter of 1997, except for the annual maintenance outages of Olkiluoto plant units and the Midsummer outage at Olkiluoto 2 due to reduced demand for electricity. There were also brief interruptions in power operation at the Olkiluoto plant units due to three reactor scrams. All plant units are undergoing long-term test operation at upgraded reactor power level which has been approved by STUK The load factor average of all plant units was 88.7 %. One event in the second quarter of 1997 was classified level 1 on the INES. The event in question was a scram at Olkiluoto 1 which was caused by erroneous opening of switches. Other events in this quarter were level 0. Occupational doses and radioactive releases off-site were below authorized limits. Radioactive substances were measurable in samples collected around the plants in such quantities only as have no bearing on the radiation exposure of the population. (orig.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-01-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-04-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1957-10-15

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

  5. Operation of Finnish nuclear power plants. Quarterly report, 3rd quarter 1997

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1998-04-01

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations relating to nuclear and radiation safety that the Radiation and Nuclear Safety Authority of Finland (STUK) considers safety significant. Safety improvements at the plants are also described. The Report also includes a summary of the radiation safety of plant personnel and of the environment and tabulated data on the plants' production and load factors. The Finnish nuclear power plant units were in power operation in the third quarter of 1997, except for the annual maintenance outages of Loviisa plant units which lasted well over a month in all. There was also a brief interruption in electricity generation at Olkiluoto 1 for repairs and at Olkiluoto 2 due to a disturbance at the turbine plant. All plant units were in long-term test operation at upgraded reactor power level approved by STUK. The load factor average of all plant units was 87.6 %. One event in the third quarter was classified level 1 on the International Nuclear Event Scale (INES). It was noted at Loviisa 2 that one of four pressurized water tanks in the plant unit's emergency cooling system had been inoperable for a year. Other events in this quarter were INES level 0. Occupational doses and radioactive releases off-site were below authorized limits. Radioactive substances were measurable in samples collected around the plants in such quantities only as have no bearing on the radiation exposure of the population. (orig.)

  6. Operation of Finnish nuclear power plants. Quarterly report 4th quarter, 1994 and annual summary

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1995-05-01

    The Loviisa NPP units were in power operation the whole last quarter, with the exception of a reactor scram at Loviisa 1. The load factor average of all Finnish plant units was 100.2 %. The annual average was 90.0 %. All events in the fourth annual quarter were assigned level 0 (no safety significance) on the international INES scale. Four events in 1994 were classified level 1 (an anomaly). The Finnish Centre for Radiation and Nuclear Safety in December approved Imatran Voima Oy's application to extend the operation of the reactor pressure vessel of Loviisa 2 until the annual maintenance outage of 2010. During this quarter, a batch of spent fuel from Loviisa power plant was transported to Russia. Occupational doses and radioactive releases off-site were below authorised limits. Only such quantities of plant-based radioactive materials were measurable in samples collected around the plants as have no bearing on the radiation exposure of the population. The report includes a summary of all the items described in the Quarterly Reports of 1994. (8 figs., 4 tabs.)

  7. Operation of Finnish nuclear power plants. Quarterly report, 3rd quarter 1996

    International Nuclear Information System (INIS)

    Sillanpaeae, T.

    1997-02-01

    Quarterly Reports on the operation of Finnish nuclear power plants describe events and observations relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety (STUK) considers safety significant. Safety improvements at the plants are also described. The Report also includes a summary of the radiation safety of plant personnel and of the environment and tabulated data on the plants' production and load factors. In the third quarter of 1996, the Finnish nuclear power plant units were in power operation except for the annual maintenance outages of Loviisa plant units and a shutdown at Olkiluoto 1 to identify and repair malfunctions of a high pressure turbine control valve. The load factor average of all plant units was 77.2%. Events in the third quarter of 1996 were classified level 0 on the International Nuclear Event Scale. Occupational doses and radioactive releases off-site were below authorised limits. Radioactive substances were measurable in samples collected around the plants in such quantities only as have no bearing on the radiation exposure of the population. The names of Teollisuuden Voima Oy's plant units have changed. Olkiluoto 1 and Olkiluoto 2 now replace the names TVO I and TVO II previously used in quarterly reports. (orig.)

  8. Operation of Finnish nuclear power plants. Quarterly report 4th quarter, 1994 and annual summary

    Energy Technology Data Exchange (ETDEWEB)

    Tossavainen, K [ed.

    1995-05-01

    The Loviisa NPP units were in power operation the whole last quarter, with the exception of a reactor scram at Loviisa 1. The load factor average of all Finnish plant units was 100.2 %. The annual average was 90.0 %. All events in the fourth annual quarter were assigned level 0 (no safety significance) on the international INES scale. Four events in 1994 were classified level 1 (an anomaly). The Finnish Centre for Radiation and Nuclear Safety in December approved Imatran Voima Oy`s application to extend the operation of the reactor pressure vessel of Loviisa 2 until the annual maintenance outage of 2010. During this quarter, a batch of spent fuel from Loviisa power plant was transported to Russia. Occupational doses and radioactive releases off-site were below authorised limits. Only such quantities of plant-based radioactive materials were measurable in samples collected around the plants as have no bearing on the radiation exposure of the population. The report includes a summary of all the items described in the Quarterly Reports of 1994. (8 figs., 4 tabs.).

  9. Operation of Finnish nuclear power plants. Quarterly report, 1st quarter 1998

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1998-11-01

    Quarterly reports on the operation of Finnish NPPs describe events and observations relating to nuclear and radiation safety that the Radiation and Nuclear Safety Authority (STUK) considers safety significant. Safety improvements at the plants are also described. The report includes a summary of the radiation safety of plant personnel and the environment and tabulated data on the plants' production and load factors. The Finnish NPP units were in power operation for the whole first quarter of 1998. All the units were in long-term test operation at uprated power level authorised by STUK. The load factor average of the plant units was 100.8%. An oil leak at Olkiluoto NPP Unit 2 caused an ignition that was promptly extinguished. A subsequent appraisal of the event disclosed deficiencies in the functioning of the plant unit's operating organization and the event was classified INES level 1. Other events in this quarter had no bearing on nuclear or radiation safety. Occupational doses and radioactive releases off-site were below authorized limits. Radioactive substances were measurable in samples collected around the plants in such quantities only as have no bearing on the radiation exposure of the population. (orig.)

  10. Regulatory and technical reports (abstract index journal). Compilation for third quarter 1997, July--September

    International Nuclear Information System (INIS)

    Stevenson, L.L.

    1998-01-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. This report contains the third quarter 1997 abstracts

  11. Operation of Finnish nuclear power plants. Quarterly report 3rd quarter, 1994

    Energy Technology Data Exchange (ETDEWEB)

    Tossavainen, K. [ed.

    1995-03-01

    Quarterly Reports on the operation of Finnish nuclear power plants describe nuclear and radiation safety related events and observations which the Finnish Centre for Radiation and Nuclear Safety (STUK) considers safety significant. Safety improvements at the plants and general matters relating to the use of nuclear energy are also reported. A summary of the radiation safety of plant personnel and of the environment, and tabulated data on the plants` production and load factors are also given. (4 figs., 4 tabs.).

  12. Operation of Finnish nuclear power plants. Quarterly report 3rd quarter, 1994

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1995-03-01

    Quarterly Reports on the operation of Finnish nuclear power plants describe nuclear and radiation safety related events and observations which the Finnish Centre for Radiation and Nuclear Safety (STUK) considers safety significant. Safety improvements at the plants and general matters relating to the use of nuclear energy are also reported. A summary of the radiation safety of plant personnel and of the environment, and tabulated data on the plants' production and load factors are also given. (4 figs., 4 tabs.)

  13. quarters

    Directory of Open Access Journals (Sweden)

    Elena Grigoryeva

    2016-10-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

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

  15. Operation of Finnish nuclear power plants. Quarterly report 3rd, quarter 1995

    Energy Technology Data Exchange (ETDEWEB)

    Sillanpaeae, T [ed.

    1996-05-01

    Quarterly Reports on the operation of Finnish nuclear power plants describe events and observations relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety (STUK) considers safety significant. Safety improvements at the plants are also described. The Report includes a summary of the radiation safety of plant personnel and of the environment and tabulated data on the plants` production and load factors. Except for the annual maintenance outages of Loviisa plant units and for TVO II`s brief outage to repair a failed component, Finnish nuclear power plant units were in power operation in the third quarter of 1995. The load factor average of all plant units was 90.4 %. Events in this quarter were level 0 on the INES scale. Occupational doses and radioactive releases off-site were below authorised limits. Radioactive substances were measurable in samples collected around the plants in such quantities only as have no bearing on the radiation exposure of the population. (orig.) (4 figs., 4 tabs.).

  16. Operation of Finnish nuclear power plants. Quarterly report 3rd, quarter 1995

    International Nuclear Information System (INIS)

    Sillanpaeae, T.

    1996-05-01

    Quarterly Reports on the operation of Finnish nuclear power plants describe events and observations relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety (STUK) considers safety significant. Safety improvements at the plants are also described. The Report includes a summary of the radiation safety of plant personnel and of the environment and tabulated data on the plants' production and load factors. Except for the annual maintenance outages of Loviisa plant units and for TVO II's brief outage to repair a failed component, Finnish nuclear power plant units were in power operation in the third quarter of 1995. The load factor average of all plant units was 90.4 %. Events in this quarter were level 0 on the INES scale. Occupational doses and radioactive releases off-site were below authorised limits. Radioactive substances were measurable in samples collected around the plants in such quantities only as have no bearing on the radiation exposure of the population. (orig.) (4 figs., 4 tabs.)

  17. Operation of Finnish nuclear power plants. Quarterly report, 4th quarter 1996

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1997-05-01

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety (STUK) considers safety significant. Safety improvements at the plants are also described. The report also includes a summary of the radiation safety of plant personnel and of the environment and tabulated data on the plants's production and load factors. In the fourth quarter of 1996, the Finnish nuclear power plant units were in power operation except for the annual maintenance outage of Loviisa 2 and a shutdown at Olkiluoto 1 to repair a condensate system stop valve. The load factor average of all plant units was 96.5%. Events in the fourth quarter of 1996 were level 0 on the International Nuclear Event Scale. Occupational doses and radioactive releases off-site were below authorised limits. Radioactive substances were measurable in samples collected around the plants in such quantities only as have no bearing on the radiation exposure of the population. (orig.)

  18. Operation of Finnish nuclear power plants. Quarterly report, 2nd quarter, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Tossavainen, K. [ed.

    1995-10-01

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety (STUK) considers safety significant. Fasety improvements at the plants are also described. The report includes a summary of the radiation safety of plant personnel and of the evironment and tabulated data on the plants` production and load factors. Except for the annual maintenance outages of the TVO plant units and for TVO II`s Midsummer outage which was due to low electricity demand, the Finnish nuclear power plants were in power operation during the second quarter of 1995. The load factor average of all four plant units was 91.2 %. Events during the second annual quarter were level 0 on the INES scale. Occupational doses and radioactive releases off-site were below authorized limits. Radioactive substances were measurable in samples collected around the plants in such quantities only as have no bearing on the radiation exposure of the population. (4 figs., 4 tabs.).

  19. Yucca Mountain Site Characterization Project: Technical Data Catalog (quarterly supplement), June 30, 1994

    International Nuclear Information System (INIS)

    1994-01-01

    The DOE/NRC Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the date, place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated September 30, 1993, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1994

  20. Mechanism for Clastogenic Activity of Naphthalene. Quarterly Technical Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    Buchholz, B. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-02-05

    The project has two main goals: 1) Identify the types of adducts naphthalene (NA) forms with DNA and 2) determine whether adduct formation correlates with site selective tumor formation in defined subcompartments of the respiratory tract (respiratory and olfactory nasal epithelium and airways of mice, rats and rhesus monkeys). Five tasks are associated with the completion of the goals. Task 1: Contracting and Animal Use Approvals. IACUC and ACURO approvals are complete. The subcontract with UC Davis (UCD) was executed in December 2014. Task 2: Perform In Vitro Study for Goal 1. Rat and mouse samples exposures completed. Monkey samples need to be exposed in next quarter. Task 3: Perform In Vitro Study for Goal 2. Mouse and rat ex vivo exposures completed. Monkey samples need to be completed in the next quarter. Task 4: Sample Preparation and Analysis. Mouse and Rat Goal 2 samples completed. Monkey samples remain to be done for Goal 2. Rat samples completed for Goal 1. Mouse and Monkey samples for Goal 1 need to be completed. Task 5: Data Interpretation and Reporting. Poster will be presented at 2016 Society of Toxicology Meeting. Outline for paper on adduct formation complete and similar to poster for SOT meeting.

  1. Regulatory and technical reports: (Abstract index journal). Compilation for first quarter 1997, January--March

    International Nuclear Information System (INIS)

    Sheehan, M.A.

    1997-06-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. This compilation is published quarterly and cummulated annually. Reports consist of staff-originated reports, NRC-sponsored conference reports, NRC contractor-prepared reports, and international agreement reports

  2. Quarterly technical progress report, February 1, 1996--April 30, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-28

    This report from the Amarillo National REsource Center for PLutonium provides research highlights and provides information regarding the public dissemination of information. The center is a a scientific resource for information regarding the issues of the storage, disposition, potential utilization and transport of plutonium, high explosives, and other hazardous materials generated from nuclear weapons dismantlement. The center responds to informational needs and interpretation of technical and scientific data raised by interested parties and advisory groups. Also, research efforts are carried out on remedial action programs and biological/agricultural studies.

  3. Power systems development facility. Quarterly technical progress report, July 1--September 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    This quarterly technical progress report summarizes work completed during the Second Quarter of the Second Budget Period, July 1 through September 30, 1993, under the Department of Energy (DOE) Cooperative Agreement No. DE-FC21-90MC25140 entitled ``Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion.`` The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scaleup of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the existing Transport Reactor gas source and Hot Gas Cleanup Units: Carbonizer/Pressurized Circulating Fluidized Bed Gas Source. Hot Gas Cleanup Units to mate to all gas streams; Combustion Gas Turbine; and Fuel Cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF). The major emphasis during this reporting period was continuing the detailed design of the facility.

  4. Thermoelectric materials evaluation program. Quarterly technical task report No. 46

    International Nuclear Information System (INIS)

    Hampl, E.F. Jr.

    1976-02-01

    This forty-sixth Technical Task Report prepared under contract E(11-1)-2331 with the U.S. AEC and U.S. ERDA covers the performance period from October 1, 1975, to December 31, 1975. Highlights include the following tasks: N-type material development (material synthesis--gadolinium selenide compositions; material analyses; material processing; element contacting; ingradient compatibility and life testing; mechanical property characterization), TPM-217 P-type characterization (material preparation and analyses; element contacting; thermodynamic stability; isothermal chemical compatibility; ingradient compatibility and ingradient life testing; performance mapping of contacted and noncontacted elements; high-temperature partitioned P-legs), couple development (design and development of TPM-217/gadolinium selenide rare earth chalcogenide couple; design and development of TPM-217/3N-PbTe couples; advanced generator concepts), module development, liaison with Jet Propulsion Laboratory and material supply, liaison with GGA, and program management. 24 figures, 27 tables

  5. Second quarter technical progress report for Thermally Modified Sand

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-14

    The objective was to have the Alaska Department of Transportation & Public Facilities Operation & Maintenance Section use Thermally Modified Sand (TMS) for treatment of icy state roadways. The project included the evaluation on the workability of a large stockpile of TMS material left undisturbed throughout the 1993/94 winter season.

  6. Yucca Mountain Site Characterization Project: Technical data catalog,(quarterly supplement)

    International Nuclear Information System (INIS)

    1993-01-01

    The June 1, 1985, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the Catalog is published at the end of each fiscal year

  7. Technical Division quarterly progess report, July 1--September 30, 1977

    Energy Technology Data Exchange (ETDEWEB)

    Slansky, C.M.; Musgrave, B.C.; Dickey, B.R.; Rohde, K.L.

    1977-10-01

    Results are presented on the fluidized-bed calcination of simulated radioactive waste from the reprocessing of spent commercial nuclear fuel, on the post treatment of the calcine, and on the removal of actinide elements from the waste prior to calcination. Other programs include the development of storage technology for {sup 85}Kr waste; a study of the hydrogen mordenite catalyzed reaction between NO{sub x} and NH{sub 3}; the adsorption and storage of {sup 129}I on silver exchanged mordenite; physical properties, materials of construction, and unit operations studies on the evaporation of high-level waste; the behavior of volatile radionuclides during the combustion of HTGR graphite-based fuel; and the use of the uranium-ruthenium system in age-dating uranium ore bodies.

  8. Technical Division quarterly progress report, April 1--June 30, 1977

    Energy Technology Data Exchange (ETDEWEB)

    Slansky, C.M.; Dickey, B.R.; Musgrave, B.C.; Rohde, K.L.

    1977-07-01

    Fuel Cycle Research and Development: Results are presented on the fluidized-bed calcination of high-level radioactive waste from reprocessing on the post treatment of the calcine, and on the removal of actinide elements from the waste prior to calcination. Other projects include the development of storage technology for /sup 85/Kr waste; a study of the hydrogen mordenite catalyzed reaction between NO/sub x/ and NH/sub 3/; the adsorption and storage of /sup 129/I on silver exchanged mordenite; physical properties, materials of construction, and unit operations studies on the evaporation of high-level waste; the behavior of volatile radionuclides during the combustion of HTGR graphite-based fuel; and the use of the uranium-ruthenium system in age-dating uranium ore bodies. Special Materials Production: The long-term management of defense waste from the ICPP covers postcalcination treatment of ICPP calcined waste; the removal of actinide elements from first-cycle raffinate; the retrieval and handling of calcined waste from ICPP storage vaults; and the preparation of the ''Defense Waste Document''. Process improvements are reported on the Fluorinel headend process for Zircaloy-clad fuels and on uranium accountability measurements. Other development results cover the process for recovering spent Rover fuel, buried pipeline transfer systems, support to the Waste Management Program, and effluent monitoring methods evaluation and development. Other Projects Supporting Energy Development: In this category are studies on nuclear materials security; application of a liquid-solid fluidized-bed heat exchanger to the recovery of geothermal heat; in-plant reactor source term measurements; burnup methods for fast breeder reactor fuels; absolute thermal fission yield measurements; analytical support to light water breeder reactor development; research on analytical methods; and the behavior of environmental species of iodine.

  9. Regulatory and technical reports. Compilation for second quarter 1982, April to June

    International Nuclear Information System (INIS)

    1982-08-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, and NUREG/CR-XXXX. A detailed explanation of the entries precedes each index

  10. Technical data base quarterly report, April--June 1992; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-09-01

    The acquisition and development of technical data are activities that provide the information base from which the Yucca mountain Site will be characterized and may P-ventually be licensed as a high-level waste repository. The Project Technical Data Base (TDB) is the repository for the regional and site-specific technical data required in intermediate and license application analyses and models. The TDB Quarterly Report provides the mechanism for identifying technical data currently available from the Project TDB. Due to the variety of scientific information generated by YMP activities, the Project TDB consists of three components, each designed to store specific types of data. The Site and Engineering Properties Data Base (SEPDB) maintains technical data best stored in a tabular format. The Geographic Nodal Information Study and Evaluation System (GENISES), which is the Geographic Information System (GIS) component of the Project TDB, maintains spatial or map-like data. The Geologic and Engineering Materials Bibliography of Chemical Species (GEMBOCHS) data base maintains thermodynamic/geochemical data needed to support geochemical reaction models involving the waste package and repository geochemical environment. Each of these data bases are addressed independently within the TDB Quarterly Report.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  12. Regulatory and technical reports: compilation for third quarter 1982 July-September

    International Nuclear Information System (INIS)

    1982-11-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, and NUREG/CR-XXXX. This precede the following indexes: Contractor Report Number Index; Personal Author Index; Subject Index; NRC Originating Organization Index (Staff Reports); NRC Contract Sponsor Index (Contractor Reports); Contractor Index; and Licensed Facility Index

  13. Long-term high-level waste technology. Composite quarterly technical report, July-September 1980

    International Nuclear Information System (INIS)

    Cornman, W.R.

    1981-02-01

    This composite quarterly technical report summarizes work performed at participating sites to immobilize high-level radioactive wastes. The technical information included in this report is structured along the lines of the Work Breakdown Structure adopted for use in the High-Level Waste Management Technology (WBS) program. The functions and work elements of the WBS are as follows: function 1 - program management and support, which includes work elements of management and budget, environmental and safety assessments, and other support; function 2 - waste preparation, which includes in-situ storage or disposal, waste retrieval, and separation and concentration; function 3 - waste fixation with work elements of waste form development and characterization, and process and equipment development; and function 4 - final handling which includes canister development and characterization, and onsite storage or disposal

  14. 77 FR 6007 - Quarterly Listings; Safety Zones, Security Zones, Special Local Regulations, Drawbridge Operation...

    Science.gov (United States)

    2012-02-07

    ...] Quarterly Listings; Safety Zones, Security Zones, Special Local Regulations, Drawbridge Operation... they could be published in the Federal Register. This notice lists temporary safety zones, security... the safety and security needs within their jurisdiction; therefore, District Commanders and COTPs have...

  15. The French Space Operation Act: Technical Regulations

    Science.gov (United States)

    Trinchero, J. P.; Lazare, B.

    2010-09-01

    The French Space Operation Act(FSOA) stipulates that a prime objective of the National technical regulations is to protect people, property, public health and the environment. Compliance with these technical regulations is mandatory as of 10 December 2010 for space operations by French space operators and for space operations from French territory. The space safety requirements and regulations governing procedures are based on national and international best practices and experience. A critical design review of the space system and procedures shall be carried out by the applicant, in order to verify compliance with the Technical Regulations. An independent technical assessment of the operation is delegated to CNES. The principles applied when drafting technical regulations are as follows: requirements must as far as possible establish the rules according to the objective to be obtained, rather than how it is to be achieved; requirements must give preference to international standards recognised as being the state of the art; requirements must take previous experience into account. Technical regulations are divided into three sections covering common requirements for the launch, control and return of a space object. A dedicated section will cover specific rules to be applied at the Guiana Space Centre. The main topics addressed by the technical regulations are: operator safety management system; study of risks to people, property, public health and the Earth’s environment; impact study on the outer space environment: space debris generated by the operation; planetary protection.

  16. Operation of Finnish nuclear power plants. Quarterly report, 2. quarter 1988

    International Nuclear Information System (INIS)

    Koponen, H.

    1988-12-01

    This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environement

  17. Operation of Finnish nuclear power plants. Quarterly report 3. quarter 1987

    International Nuclear Information System (INIS)

    Haenninen, R.

    1988-06-01

    This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel o the environment

  18. Operation of Finnish nuclear power plants. Quarterly report, 3. quarter 1988

    International Nuclear Information System (INIS)

    Koponen, H.

    1989-02-01

    This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment

  19. Regulatory and technical reports (abstract index journal). Volume 20, No. 2: Compilation for second quarter April--June 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC`s intention to publish this compilation quarterly and to cumulate it annually.

  20. Technical Issues Map for the NHI System Interface and Support Systems Area: 2nd Quarter FY07

    International Nuclear Information System (INIS)

    Steven R. Sherman

    2007-01-01

    This document provides a mapping of technical issues associated with development of the Next Generation Nuclear Plant (NGNP) intermediate heat transport loop and nuclear hydrogen plant support systems to the work that has been accomplished or is currently underway in the 2nd quarter of FY07

  1. Regulatory and technical reports (abstract index journal). Volume 20, No. 2: Compilation for second quarter April--June 1995

    International Nuclear Information System (INIS)

    1995-09-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually

  2. Technical support for nuclear power operations

    International Nuclear Information System (INIS)

    1999-04-01

    This report prepared by the group of senior experts from nuclear operating organizations in Member states, addresses the problem of improving the operating performance of nuclear power plants. Safe and reliable operation is essential for strengthening the viability of nuclear power in the increasingly competitive market of electric power. Basic principles and requirements concerning technical procedures and developed practices are discussed. Report reflects the best current international practices and presents those management initiatives that go beyond the mandated regulatory compliance and could lead to enhancement od operational safety and improved plant performance. By correlating experiences and presenting collective effective practices it is meant to assist nuclear power plant managers in achieving improvement in operation through the contribution of effective technical support

  3. Automated Array Assembly, Phase 2. Quarterly technical progress report, fourth quarter 1977. Texas Instruments report No. 03-77-56

    Energy Technology Data Exchange (ETDEWEB)

    Carbajal, B.G.

    1978-01-01

    The Automated Array Assembly Task, Phase 2 of the Low Cost Silicon Solar Array (LSSA) Project, is a process development task. This contract includes solar cell module process development activities in the areas of Surface Preparation, Plasma Processing, Diffusion, Cell Processing and Module Fabrication. In addition, a High Efficiency Cell Development Activity is included. During this quarter, effort was concentrated on wafer etching for saw damage removal, establishing a standard phosphorous diffusion process and a baseline solar cell process as a test bed, designing a large area square cell including test sites, analyzing module layouts for optimum packing efficiency and fabricating the first Tandem Junction Cells (TJC) for this contract. A TJC with backside contacts gave 15.1% efficiency at AM1.

  4. Orcas Power and Light Company [fourth quarterly] technical progress report, July--September 1992

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-31

    After a year of operating the G-Van, OPALCO concluded that the company transportation needs were not being met by the G-Van. The previous quarterly report mentioned battery problems with the Solectria (No. 51). This problem is one of reduced range and power and has been determined to be caused by one or more individual monoblock failures. The local Solectria representative and Solectria headquarters personnel have been aware of this unsatisfactory condition and are continuing their attempt to solve it. The Solectria and G-Van continue to be used intermittently by company personnel for errands and engineering trips. Generally, the smaller, compact size of the Solectria make it the most preferred by company drivers. Clearly the G-Van is not selected for use because of its size and weight. It is important to note that the driver dissatisfaction is not related to the fact that it is an electric van, but more its lack of maneuverability.

  5. Orcas Power and Light Company [fourth quarterly] technical progress report, July--September 1992

    Energy Technology Data Exchange (ETDEWEB)

    1992-01-01

    After a year of operating the G-Van, OPALCO concluded that the company transportation needs were not being met by the G-Van. The previous quarterly report mentioned battery problems with the Solectria (No. 51). This problem is one of reduced range and power and has been determined to be caused by one or more individual monoblock failures. The local Solectria representative and Solectria headquarters personnel have been aware of this unsatisfactory condition and are continuing their attempt to solve it. The Solectria and G-Van continue to be used intermittently by company personnel for errands and engineering trips. Generally, the smaller, compact size of the Solectria make it the most preferred by company drivers. Clearly the G-Van is not selected for use because of its size and weight. It is important to note that the driver dissatisfaction is not related to the fact that it is an electric van, but more its lack of maneuverability.

  6. 76 FR 9646 - Quarterly Listings; Safety Zones, Security Zones, Special Local Regulations, Drawbridge Operation...

    Science.gov (United States)

    2011-02-22

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard 33 CFR Parts 100, 117, 147, and 165 [USCG-2010-0399] Quarterly Listings; Safety Zones, Security Zones, Special Local Regulations, Drawbridge Operation Regulations and Regulated Navigation Areas AGENCY: Coast Guard, DHS. ACTION: Notice of expired temporary rules...

  7. 76 FR 70342 - Quarterly Listings; Safety Zones, Security Zones, Special Local Regulations, Drawbridge Operation...

    Science.gov (United States)

    2011-11-14

    ...] Quarterly Listings; Safety Zones, Security Zones, Special Local Regulations, Drawbridge Operation... published in the Federal Register. This notice lists temporary safety zones, security zones, special local... Commanders and Captains of the Port (COTP) must be immediately responsive to the safety and security needs...

  8. Long-term high-level waste technology. Composite quarterly technical report, January-March 1981

    International Nuclear Information System (INIS)

    Cornman, W.R.

    1981-08-01

    This composite quarterly technical report summarizes work performed at participating sites to immobilize high-level radioactive wastes. The report is structured along the lines of the Work Breakdown Structure adopted for use in the High-Level Waste Management Technology program. These are: (1) program management and support with subtasks of management and budget, environmental and safety assessments, and other support; (2) waste preparation with subtasks of in-situ storage or disposal, waste retrieval, and separation and concentration; (3) waste fixation with subtasks of waste form development and characterization, and process and equipment development; and (4) final handling with subtasks of canister development and characterization and onsite storage or disposal. Some of the highlights are: preliminary event trees defining possible accidents were completed in the safety assessment of continued in-tank storage of high-level waste at Hanford; two low-cost waste forms (tailored concrete and bitumen) were investigated as candidate immobilization forms at the Hanford in-situ disposal studies of high-level waste; in comparative impact tests at the same impact energy per specimen volume, the same mass of respirable sizes was observed at ANL for SRL Frit 131 glass, SYNROC B ceramic, and SYNROC D ceramic; leaching tests were conducted on alkoxide glasses; glass-ceramic, concrete, and SYNROC D; a process design description was written for the tailored ceramic process

  9. An analysis of auditory cues for inclusion in a close quarters battle room clearing operation

    OpenAIRE

    Greenwald, Thomas W.

    2002-01-01

    Approved for public release, distribution is unlimited The purpose of this thesis is to examine which auditory cues need to be included in a virtual representation of a Close Quarters Combat Room Clearing Operation. Future missions of the United States Armed Forces, especially those of the Army and Marine Corps, are increasingly likely to be conducted in cities or built-up areas. A critical need exists for MOUT (Military Operations in Urban Terrain) training by our armed forces, and the en...

  10. GBRN/DOE Project: Dynamic enhanced recovery technologies. Quarterly technical report, January 1994--March 1994

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, R.N.

    1994-04-15

    Global Basins Research Network will perform a field demonstration of their ``Dynamic Enhanced Recovery Technology`` to test the concept that the growth faults in EI-330 field are conduits through which producing reservoirs are charged and that enhanced production can be developed by producing directly from the fault zone. The site, operated by Penzoil, is located in 250 feet of water the productive depth intervals include 4000 to 9000 feet. Previous work, which incorporated pressure, temperature, fluid flow, heat flow, seismic, production, and well log data, indicated active fluid flow along fault zones. The field demonstration will be accomplished by drilling and production test of growth fault systems associated with the EI-330 field. The project utilizes advanced 3-D seismic analysis, geochemical studies, structural and stratigraphic reservoir characterization, reservoir simulation, and compact visualization systems. The quarterly progress reports contains accomplishments to date for the following tasks: Management start-up; database management; field and demonstration equipment; reservoir characterization, modeling; geochemistry; and data integration.

  11. [Dynamic enhanced recovery techniques]. Quarterly technical report, April 1994--June 1994

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, R.N.

    1994-07-15

    Global Basins Research Network will perform a field demonstration of their ``Dynamic Enhanced Recovery Technology`` to test the concept that the growth of faults in Eugene Island Block 330 (EI-330 field) are conduits through which producing reservoirs are charged and that enhanced production can be developed by producing directly from the fault zone. The site, operated by Penzoil, is located in 250 feet of water and the productive depth intervals include 4000 to 9000 feet. The field demonstration will be accomplished by drilling and production testing of growth fault systems associated with the EI-330 field. The project utilizes advanced 3-D seismic analysis, geochemical studies, structural and stratigraphic reservoir characterization, reservoir simulation, and compact visualization systems. In this quarterly report, progress reports are presented for the following tasks: Task one--management start-up; Task two--database management; Task three--field demonstration experiment; Task four--reservoir characterization; Task five--modeling; Task six--geochemistry; and Task seven--data integration.

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

    Energy Technology Data Exchange (ETDEWEB)

    Francfort, J.E. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); Bassett, R.R. [Sandia National Labs., Albuquerque, NM (United States); Briasco, S. [Los Angeles Dept. of Water and Power, CA (United States)] [and others

    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.

  13. Data validation report for the 100-KR-4 operable unit first quarter, 1994

    International Nuclear Information System (INIS)

    Krug, A.D.

    1994-01-01

    Samples were obtained from the 100-KR-4 Operable Unit first Quarter 1994 Groundwater Sampling event. The data from the chemical analysis of fifty-eight samples from this sampling event and their related quality assurance samples were reviewed and validated to verify that reported samples results were of sufficient quality to support decisions regarding remedial actions performed at this site. Information fro the sampling event and the information validation processes are presented in this document

  14. IAEA Technical Co-operation activities: Africa

    International Nuclear Information System (INIS)

    Bakr, A.A.

    1976-01-01

    In 1975 Tanzania became the newest African Member State of the International Atomic Energy Agency, bringing the total African membership of the Agency up to 25 countries. The other African Member States are: Algeria; United Republic of Cameroon; Egypt; Ethiopia; Gabon; Ghana; Ivory Coast; Kenya; Liberia; Libyan Arab Republic; Madagascar; Mali; Mauritius; Morocco; Niger; Nigeria; Senegal; Sierra Leone; South Africa; Sudan; Tunisia; Uganda; Zaire; Zambia. Membership of the Agency entitles these countries to receive assistance both from the Regular Programme of the Agency and from UNDP resources, while non-Member States in the region only receive Agency assistance financed from the latter source. Any attempt to look at the technical co-operation programme in Africa must start by stressing the wide differences between African countries in their level of scientific and technical development ranging from countries with advanced atomic energy programmes to countries just crossing the threshold towards the peaceful use of nuclear energy. Perhaps the most striking and marked difference is in the quality and number of nuclear energy scientists and technologists available. In view of this, the technical assistance programme in the African context has been a selective one, guided by considerations of pragmatism and responsiveness to particular requirements of the different individual countries and not by any doctrinaire or ready-made strategy for assistance. (author)

  15. Pulverized coal firing of aluminum melting furnaces. Quarterly technical progress report, October 1-December 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    West, C E

    1980-10-01

    Heaviest acitivity this quarter has been in the area of system design and specification and purchase of system components. Mechanical design is now complete. The design of electrical power, process control and data acquisition systems has begun. Combustor design meetings with General Electric Space Science Labs have resulted in an increasing awareness that analytical flow field modeling of the cyclonic combustor could not only enhance current understanding of the process but also broaden the future scope of implementation. A proposal to add specific additional modeling tasks was presented to the Department of Energy, and is included herein in Appendix B. Equipment procurement will continue and system construction will begin during the next quarter.

  16. Amarillo National Resource Center for Plutonium quarterly technical progress report, August 1, 1997--October 31, 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    This report summarizes activities of the Amarillo National Resource Center for Plutonium during the quarter. The report describes the Electronic Resource Library; DOE support activities; current and future environmental health and safety programs; pollution prevention and pollution avoidance; communication, education, training, and community involvement programs; and nuclear and other material studies, including plutonium storage and disposition studies.

  17. Evaluation of using cyclocranes to support drilling and production of oil and gas in wetland areas. Fifth quarterly technical progress report, Third quarter, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Eggington, W.J.

    1993-12-31

    The planned program falls under wetlands area research related to drilling, production, and transportation of oil and gas resources. Specifically the planned program addresses an evaluation of using cyclocraft to transport drill rigs, mud, pipes and other materials and equipment in a cost effective and environmentally safe manner to support oil and gas drilling and production operations in wetland areas. The cyclocraft is a proven hybrid aircraft that utilizes aerostatic and aerodynamic lift. This type of aircraft has considerable payload capacity, VTOL capability, high controllability, low operating cost, low downwash and high safety. The benefits of using a cyclocraft to transport drill rigs and materials over environmentally-sensitive surfaces would be significant. The cyclocraft has considerable cost and operational advantages over the helicopter. In 1992, Task 1, Environmental Considerations, and Task 2, Transport Requirements, were completed. In the first two quarters of 1993, Task 3, Parametric Analysis, Task 4, Preliminary Design, and Task 6, Ground Support, were completed. Individual reports containing results obtained from each of these tasks were submitted to DOE. In addition, through June 30, 1993, a Subscale Test Plan was prepared under Task 5, Subscale Tests, and work was initiated on Task 7, Environmental Impacts, Task 8, Development Plan, Task 9, Operating Costs, and Task 10, Technology Transfer.

  18. Evaluation of using cyclocranes to support drilling and production of oil and gas in wetland areas. Fourth quarterly technical progress report, Second quarter, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Eggington, W.J.

    1993-09-01

    The planned program falls under wetlands area research related to drilling, production, and transportation of oil and gas resources. Specifically the planned program addresses an evaluation of using cyclocraft to transport drill rigs, mud, pipes and other materials and equipment in a cost effective and environmentally safe manner to support oil and gas drilling and production operations in wetland areas. The cyclocraft is a proven hybrid aircraft that utilizes aerostatic and aerodynamic lift. This type of aircraft has considerable payload capacity, VTOL capability, high controllability, low operating cost, low downwash and high safety. The benefits of using a cyclocraft to transport drill rigs and materials over environmentally-sensitive surfaces would be significant. The cyclocraft has considerable cost and operational advantages over the helicopter. The major activity during the second quarter of 1993 was focussed on completion of Task 4, Preliminary Design. The selected design has been designated H.1 Cyclocraft by MRC. Also during the report period, Task 6, Ground Support, was completed and a report containing the results was submitted to DOE. This task addressed the complete H.1 Cyclocraft system, i.e. it included the need personnel, facilities and equipment to support cyclocraft operations in wetland areas.

  19. [Geothermal system temperature-depth database and model for data analysis]. 5. quarterly technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    Blackwell, D.D.

    1998-04-25

    During this first quarter of the second year of the contract activity has involved several different tasks. The author has continued to work on three tasks most intensively during this quarter: the task of implementing the data base for geothermal system temperature-depth, the maintenance of the WWW site with the heat flow and gradient data base, and finally the development of a modeling capability for analysis of the geothermal system exploration data. The author has completed the task of developing a data base template for geothermal system temperature-depth data that can be used in conjunction with the regional data base that he had already developed and is now implementing it. Progress is described.

  20. FETC/EPRI Biomass Cofiring Cooperative Agreement. Quarterly technical report, April 1-June 30, 1997

    Energy Technology Data Exchange (ETDEWEB)

    Hughes, E.; Tillman, D.

    1997-12-01

    The FETC/EPRI Biomass Cofiring Program has accelerated the pace of cofiring development by increasing the testing activities plus the support activities for interpreting test results. Past tests conducted and analyzed include the Allen Fossil Plant and Seward Generating Station programs. On-going tests include the Colbert Fossil Plant precommercial test program, the Greenidge Station commercialization program, and the Blount St. Station switchgrass program. Tests in the formative stages included the NIPSCO cofiring test at Michigan City Generating Station. Analytical activities included modeling and related support functions required to analyze the cofiring test results, and to place those results into context. Among these activities is the fuel availability study in the Pittsburgh, PA area. This study, conducted for Duquesne Light, supports their initial investigation into reburn technology using wood waste as a fuel. This Quarterly Report, covering the third quarter of the FETC/EPRI Biomass Cofiring Program, highlights the progress made on the 16 projects funded under this cooperative agreement.

  1. Instrumentation of dynamic gas pulse loading system. Technical progress report, first quarter 1992

    Energy Technology Data Exchange (ETDEWEB)

    Mohaupt, H.

    1992-04-14

    The overall goal of this work is to further develop and field test a system of stimulating oil and gas wells, which increases the effective radius of the well bore so that more oil can flow into it, by recording pressure during the gas generation phase in real time so that fractures can be induced more predictably in the producing formation. Task 1: Complete the laboratory studies currently underway with the prototype model of the instrumentation currently being studied. Task 2: Perform field tests of the model in the Taft/Bakersfield area, utilizing operations closest to the engineers working on the project, and optimize the unit for various conditions encountered there. Task 3: Perform field test of the model in DGPL jobs which are scheduled in the mid-continent area, and optimize the unit for downhole conditions encountered there. Task 4: Analyze and summarize the results achieved during the complete test series, documenting the steps for usage of downhole instrumentation in the field, and compile data specifying use of the technology by others. Task 5: Prepare final report for DOE, and include also a report on the field tests completed. Describe and estimate the probability of the technology being commercialized and in what time span. The project has made substantial technical progress, though we are running about a month behind schedule. Expenditures are in line with the schedule. Increased widespread interest in the use of DGPL stimulation has kept us very busy. The computer modeling and test instrumentation developed under this program is already being applied to commercial operations.

  2. NST Quarterly

    International Nuclear Information System (INIS)

    1995-01-01

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

  3. NST Quarterly

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-01-01

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

  4. Salt repository project: Technical progress report for the quarter 1 April--30 June 1987

    International Nuclear Information System (INIS)

    1987-01-01

    This document reports the progress being made each quarter on the development of a geologic repository in salt for the permanent disposal of high-level nuclear waste. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Nuclear Waste Isolation, a prime contractor of the US Department of Energy (DOE) Salt Repository Project Office. The studies include work by other DOE prime contractors and by contractors to the Office of Nuclear Waste Isolation

  5. Salt Repository Project technical progress report for the quarter 1 January--31 March 1987

    International Nuclear Information System (INIS)

    1988-03-01

    This document reports the progress being made each quarter on the development of a geologic repository in salt for the permanent disposal of high-level nuclear waste. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Nuclear Waste Isolation, a prime contractor of the US Department of energy (DOE) Salt Repository Project Office. The studies include work by other DOE prime contractors and by contractors to the Office of Nuclear Waste Isolation. 23 refs., 1 fig

  6. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1994, July--September. Volume 19, Number 3

    International Nuclear Information System (INIS)

    1994-12-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issues by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/IA-XXXX. These precede the following indexes: Secondary Report Number Index, Personal Author Index, Subject Index, NRC Originating Organization Index (Staff Reports), NRC Originating Organization Index (International Agreements), NRC Contract Sponsor Index (Contractor Reports) Contractor Index, International Organization Index, Licensed Facility Index. A detailed explanation of the entries precedes each index

  7. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1996 July--September. Volume 21, Number 3

    International Nuclear Information System (INIS)

    1997-02-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/IA-XXXX. These precede the following indexes: secondary report number index; personal author index; subject index; NRC originating organization index (staff reports); NRC originating organization index (international agreements); NRC contract sponsor index (contractor reports); contractor index; international organization index; and licensed facility index. A detailed explanation of the entries precedes each index

  8. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1996 July--September. Volume 21, Number 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC`s intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/IA-XXXX. These precede the following indexes: secondary report number index; personal author index; subject index; NRC originating organization index (staff reports); NRC originating organization index (international agreements); NRC contract sponsor index (contractor reports); contractor index; international organization index; and licensed facility index. A detailed explanation of the entries precedes each index.

  9. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1994, July--September. Volume 19, Number 3

    Energy Technology Data Exchange (ETDEWEB)

    None

    1994-12-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issues by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC`s intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/IA-XXXX. These precede the following indexes: Secondary Report Number Index, Personal Author Index, Subject Index, NRC Originating Organization Index (Staff Reports), NRC Originating Organization Index (International Agreements), NRC Contract Sponsor Index (Contractor Reports) Contractor Index, International Organization Index, Licensed Facility Index. A detailed explanation of the entries precedes each index.

  10. Technical and operational assessment of molecular nanotechnology for space operations

    Science.gov (United States)

    McKendree, Thomas Lawrence

    2001-07-01

    This study assesses the performance of conventional technology and three levels of molecular nanotechnology (MNT) for space operations. The measures of effectiveness are technical performance parameters for five space transportation architectures, and the total logistics cost for an evaluation scenario with mining, market and factory locations on the Moon, Mars and asteroids. On these measures of effectiveness, improvements of 2--4 orders of magnitude are seen in chemical rockets, solar electric ion engines, solar sail accelerations (but not transit times), and in structural masses for planetary skyhooks and towers. Improvements in tether performance and logistics costs are nearer to 1 order of magnitude. Appendices suggest additional improvements may be possible in space mining, closed-environment life support, flexible operations, and with other space transportation architectures. In order to assess logistics cost, this research extends the facility location problem of location theory to orbital space. This extension supports optimal siting of a single facility serving circular, coplanar orbits, locations in elliptic planetary and moon orbits, and heuristic siting of multiple facilities. It focuses on conventional rocket transportation, and on high performance rockets supplying at least 1 m/s2 acceleration and 500,000 m/s exhaust velocity. Mathematica implementations are provided in appendices. Simple MNT allows diamond and buckytube construction. The main benefits are in chemical rocket performance, solar panel specific power, solar electric ion engine performance, and skyhook and tower structural masses. Complex MNT allows very small machinery, permitting large increases in solar panel specific power, which enables solar electric ion engines that are high performance rockets, and thus reduces total logistics costs an order of magnitude. Most Advance MNT allows molecular manufacturing, which enables self-repair, provides at least marginal improvements in nearly

  11. Radiation dechlorination of PCE and PCB in the quarter operation flow apparatus

    International Nuclear Information System (INIS)

    Mucka, V.; Silber, R.; Pospisil, M.; Camra, M.; Bartonicek, B.

    1999-01-01

    The aim of this work was to verify practical possibilities of radiation dechlorination of liquid chlorinated substrates [perchloroethylene (PCE) and polychlorinated biphenyls (PCB)] in the quarter operation flow apparatus. In this apparatus may be disposable work over 50 dm 3 of media. Radiation dechlorination of PCE proceeds more effectively as dechlorination of PCB in flow regimes, too. Radiation chemical yield of G(-OH - ) decrease with increasing applied radiation dose and at the dose 5 kGy for PCE it is 200 · 10 -2 eV -1 and for PCB this value is 55 · 10 -2 eV -1 . At increasing original concentration of PCE or PCB the G-values decreases. The radical chain mechanism of dechlorination of PCE and PCB was proposed

  12. Data validation report for the 100-HR-3 Operable Unit first quarter 1994 groundwater sampling data

    Energy Technology Data Exchange (ETDEWEB)

    Biggerstaff, R.L.

    1994-06-24

    Westinghouse-Hanford has requested that a minimum of 20% of the total number of Sample Delivery Groups be validated for the 100-HR-3 Operable Unit First Quarter 1994 Groundwater Sampling Investigation. Therefore, the data from the chemical analysis of twenty-four samples from this sampling event and their related quality assurance samples were reviewed and validated to verify that reported sample results were of sufficient quality to support decisions regarding remedial actions performed at this site. The samples were analyzed by Thermo-Analytic Laboratories (TMA) and Roy F. Weston Laboratories (WESTON) using US Environmental Protection Agency (EPA) CLP protocols. Sample analyses included: inorganics; and general chemical parameters. Forty-two samples were validated for radiochemical parameters by TMA and Teledyne.

  13. Data validation report for the 100-HR-3 Operable Unit first quarter 1994 groundwater sampling data

    International Nuclear Information System (INIS)

    Biggerstaff, R.L.

    1994-01-01

    Westinghouse-Hanford has requested that a minimum of 20% of the total number of Sample Delivery Groups be validated for the 100-HR-3 Operable Unit First Quarter 1994 Groundwater Sampling Investigation. Therefore, the data from the chemical analysis of twenty-four samples from this sampling event and their related quality assurance samples were reviewed and validated to verify that reported sample results were of sufficient quality to support decisions regarding remedial actions performed at this site. The samples were analyzed by Thermo-Analytic Laboratories (TMA) and Roy F. Weston Laboratories (WESTON) using US Environmental Protection Agency (EPA) CLP protocols. Sample analyses included: inorganics; and general chemical parameters. Forty-two samples were validated for radiochemical parameters by TMA and Teledyne

  14. Estimation of regulated term of technical systems further operation

    International Nuclear Information System (INIS)

    Strel'nikov, V.P.

    2008-01-01

    The technique of estimating the regulated term of technical systems further operation on the basis of data on failures during operation and use of probabilistic-physical model of failures (DN-distribution) is proposed

  15. Technical progress report for the quarter 1 October-31 December 1980

    International Nuclear Information System (INIS)

    1981-01-01

    This report describes the technical accomplishments on the commercial nuclear waste management programs and on the geologic disposal of nuclear wastes. The program is organized into eight tasks: systems, waste package, site, repository, regulatory and institutional, test facilities and excavations, land acquisition, and program management

  16. Technical progress report for the quarter 1 October-31 December 1980

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    This report describes the technical accomplishments on the commercial nuclear waste management programs and on the geologic disposal of nuclear wastes. The program is organized into eight tasks: systems, waste package, site, repository, regulatory and institutional, test facilities and excavations, land acquisition, and program management. (DLC)

  17. Amarillo National Resource Center for Plutonium. Quarterly technical progress report, May 1--July 31, 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    Progress is reported on research projects related to the following: Electronic resource library; Environment, safety, and health; Communication, education, training, and community involvement; Nuclear and other materials; and Reporting, evaluation, monitoring, and administration. Technical studies investigate remedial action of high explosives-contaminated lands, radioactive waste management, nondestructive assay methods, and plutonium processing, handling, and storage.

  18. Automated Array Assembly, Phase 2. Quarterly technical progress report, April-June 1979

    Energy Technology Data Exchange (ETDEWEB)

    Carbajal, B.G.

    1979-07-01

    The Automated Array Assembly Task, Phase 2 of the Low Cost Solar Array (LSA) Project is a process development task. This contract provides for the fabrication of modules from large area Tandem Junction Cells (TJC). The key activities in this contract effort are (a) Large Area TJC including cell design, process verification and cell fabrication and (b) Tandem Junction Module (TJM) including definition of the cell-module interfaces, substrate fabrication, interconnect fabrication and module assembly. The overall goal is to advance solar cell module process technology to meet the 1986 goal of a production capability of 500 megawatts per year at a cost of less than $500 per peak kilowatt. This contract will focus on the Tandem Junction Module process. During this quarter, effort was focused on design and process verification. The large area TJC design was completed and the design verification was completed. Process variation experiments led to refinements in the baseline TJC process. Formed steel substrates were porcelainized. Cell array assembly techniques using infrared soldering are being checked out. Dummy cell arrays up to 5 cell by 5 cell have been assembled using all backside contacts.

  19. Superconducting fault current limiter. Fifth quarterly technical progress report, August 8, 1978-November 7, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    Progress in the development of fault current limiters for superconducting power transmission systems is reported. The analysis and design of a magnetically switched resistive device and the experimental program were emphasized and reported. A transient heat transfer model was developed which indicates the parameters which are important in determining the thermal heating and recovery of the superconduting film. Designs for the switching coil and the S/C element were also carried out and are reported. A four-pole magnetic coil is recommended; this generates a magnetic field which is nearly perpendicular to spiral or helical S/C film geometrics. A spirally-designed, 3000 ohm limiter is shown to be able to fit within a .5 to 1m inner radius, .05 to .03 m wide, 1.3 to 3.9 m long annualr region. The experimental program has included work on materials development and on prepartion of the switching and thermal recovery experimental facility. The material development program has uncovered several serious short-comings of NbN as the S/C film material. Macroscopic holes and surface debris, and microscopic imperfections reduce the critical current density below the expected value and, in addition, cause nonuniform switching. Reasons for these effects are postulated, and a continuing, vigorous materials program is suggested in hopes of alleviating these problems. Virtually all of the experimental equipment had been installed, and so the magnetic switching and thermal recovery experiments can begin and progress during the next quarter. (LCL)

  20. ERIP invention 637. Technical progress report 2nd quarter, April 1997--June 1997

    Energy Technology Data Exchange (ETDEWEB)

    Thacker, G.W.

    1997-07-22

    This technical report describes progress in the development of the Pegasus plow, a stalk and root embedding apparatus. Prototype testing is reported, and includes the addition of precision tillage. Disease data, organic matter, and nitrogen levels results are very briefly described. Progress in marketing is also reported. Current marketing issues include test use by cotton and wheat growers, establishment of dealer relationships, incorporation of design modifications, expansion of marketing activities, and expansion of loan and lease program.

  1. Microwave plasma source for neutral-beam injection systems. Quarterly technical progress report

    International Nuclear Information System (INIS)

    1981-01-01

    The overall program is described and the technical and programmatic reasons for the decision to pursue both the RFI and ECH sources into the current hydrogen test stage is discussed. We consider the general characteristics of plasma sources in the parameter regime of interest for neutral beam applications. The operatonal characteristics, advantages and potential problems of RFI and ECH sources are discussed. In these latter two sections we rely heavily on experience derived from developing RFI and ECH ion engine sources for NASA

  2. I-NERI QUARTERLY TECHNICAL PROGRESS REPORT - JANUARY 1 - MARCH 31, 2005

    International Nuclear Information System (INIS)

    Chang Oh

    2005-01-01

    The objective of this Korean/United States/laboratory/university collaboration is to develop new advanced computational methods for safety analysis codes for very-high-temperature gas-cooled reactors (VHTGRs) and numerical and experimental validation of these computer codes. The research will improve two well-respected light water reactor transient response codes (RELAP5/ATHENA and MELCOR) in the modeling of molecular diffusion and chemical equilibrium, and to validate these codes against the VHTGR accident data, i.e., air ingress and others from the literature. The VHTGR is intrinsically safe, has a proliferation-resistant fuel cycle, and many advantages relative to light water reactors (LWRs). This study consists of five tasks for FY-03: (1) development of computational methods for the VHTGR, (2) theoretical modification of aforementioned computer codes for molecular diffusion (RELAP5/ATHENA) and modeling CO and CO 2 equilibrium (MELCOR), (3) development of a state-of-the-art methodology for VHTGR neutronic analysis and calculation of accurate power distributions and decay heat deposition rates, (4) reactor cavity cooling system experiment, and (5) graphite oxidation experiment. First quarter of Year 3: (A) Prof. NO and Kim continued Task 1. We first performed the chemical reaction test for the VELUNA pebble oxidation experiment and then the analysis of the air ingress accident for PBMR 268MWt. In the GAMMA analysis, significant rise in pebble temperature was observed at the bottom of the core due to graphite oxidation. Since the air ingress process depends on the vault conditions, further analysis coupled with more detailed vault or containment modeling would be necessary as a future study. (B) Prof. Park continued Task 2. The experiments for SNU-RCCS were continued to provide the experimental data for the validation of the thermal hydraulic code being developed at KAIST and to evaluate the performance of the system using the experiments and system analysis

  3. Solvent refined coal (SRC) process. Quarterly technical progress report, January 1980-March 1980. [In process streams

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    This report summarizes the progress of the Solvent Refined Coal (SRC) project at the SRC Pilot Plant in Fort Lewis, Wahsington, and the Process Development Unit (P-99) in Harmarville, Pennsylvania. After the remaining runs of the slurry preheater survey test program were completed January 14, the Fort Lewis Pilot Plant was shut down to inspect Slurry Preheater B and to insulate the coil for future testing at higher rates of heat flux. Radiographic inspection of the coil showed that the welds at the pressure taps and the immersion thermowells did not meet design specifications. Slurry Preheater A was used during the first 12 days of February while weld repairs and modifications to Slurry Preheater B were completed. Two attempts to complete a material balance run on Powhatan No. 6 Mine coal were attempted but neither was successful. Slurry Preheater B was in service the remainder of the quarter. The start of a series of runs at higher heat flux was delayed because of plugging in both the slurry and the hydrogen flow metering systems. Three baseline runs and three slurry runs of the high heat flux program were completed before the plant was shut down March 12 for repair of the Inert Gas Unit. Attempts to complete a fourth slurry run at high heat flux were unsuccessful because of problems with the coal feed handling and the vortex mix systems. Process Development Unit (P-99) completed three of the four runs designed to study the effect of dissolver L/D ratio. The fourth was under way at the end of the period. SRC yield correlations have been developed that include coal properties as independent variables. A preliminary ranking of coals according to their reactivity in PDU P-99 has been made. Techniques for studying coking phenomenona are now in place.

  4. Quarterly technical progress report for the period ending June 30, 1984

    Energy Technology Data Exchange (ETDEWEB)

    1984-10-01

    The Magnetohydrodynamics Program (Component Development and Integration Facility) in Butte, Montana, continued its site preparation for the TRW first-stage combustor installation. In the area of flue gas cleanup, our in-house research program is continuing its investigation into the causes of sorbent attrition in PETC's fluidized-bed copper oxide process for simultaneous SO/sub 2//NO/sub x/ removal. Interwoven with these tests is a series of spray dryer/electrostatic precipitator tests that are being conducted with the cooperation of Wheelabrator-Frye, Inc. This test series was completed this quarter, and the data show that when using a Kentucky coal, Wheelabrator-Frye's electrostatic precipitator provides excellent particulate control efficiency while using a spray dryer for sulfur dioxide removal. A unique project at Carnegie-Mellon University is looking at the concept of integrated environmental control for coal-fired power plants making use of precombustion, combustion, and postcombustion control, including systems for the simultaneous removal of more than one pollutant. The objective of this research is to develop a computer model and assessment for integrated environmental control systems that utilize conventional or advanced systems. The Liquid Phase Methanol Project Development Unit in LaPorte, Texas, was restarted after a successful shakedown run was completed. PETC has recently begun an in-house research project aimed at exploring the basic chemistry of liquefying coal in the presence of water under supercritical conditions. In the Alternative Fuels Technology Program, the Gulf Research and Development Company has completed the preliminary testing phase of its erosion test loop. Their results indicate that when pumping a coal-water slurry fuel through a flow loop, the erosion rate increases as velocity increases, suggesting a well-defined relationship between these two parameters.

  5. Decontamination Systems Information and Research Program. Quarterly technical progress report, January 1--March 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-04-01

    This reports reports the progress/efforts performed on six technical projects: 1. systematic assessment of the state of hazardous waste clean-up technologies; 2. site remediation technologies (SRT):drain- enhanced soil flushing for organic contaminants removal; 3. SRT: in situ bio-remediation of organic contaminants; 4. excavation systems for hazardous waste sites: dust control methods for in-situ nuclear waste handling; 5. chemical destruction of polychlorinated biphenyls; and 6. development of organic sensors: monolayer and multilayer self-assembled films for chemical sensors.

  6. Quarterly Performance/Technical Report of the National Marrow Donor Program

    National Research Council Canada - National Science Library

    Setterholm, Michelle

    2009-01-01

    ... a nationwide contingency response plan. Rapid Identification of Matched Donors: Increase operational efficiencies that accelerate the search process and increase patient access are key to preparedness in a contingency event...

  7. Quarterly Performance/Technical Report for July 1, 2007 to September 30, 2007

    National Research Council Canada - National Science Library

    Setterholm, Michelle

    2007-01-01

    ... a nationwide contingency response plan. 2. Rapid Identification of Matched Donors : Increase operational efficiencies that accelerate the search process and increase patient access are key to preparedness in a contingency event. 3...

  8. Quarterly Performance/Technical Report of the National Marrow Donor Program

    National Research Council Canada - National Science Library

    Coppo, Patrica A; Davis, Judy W; Spellman, Steve M

    2006-01-01

    ... a nationwide contingency response plan. 2. Rapid Identification of Matched Donors : Increase operational efficiencies that accelerate the search process and increase patient access are key to preparedness in a contingency event...

  9. Quarterly Performance/Technical Report of the National Marrow Donor Program (Trademark)

    National Research Council Canada - National Science Library

    Setterholm, Michelle

    2008-01-01

    ... a nationwide contingency response plan. 2. Rapid Identification of Matched Donors : Increase operational efficiencies that accelerate the search process and increase patient access are key to preparedness in a contingency event. 3...

  10. LOA-1: prevent accidents. Quarterly technical progress report, FRSP program - July through September 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Information related to LMFBR reactor safety is presented concerning common cause failures; shutdown by self-activated system; shutdown heat removal system operation; sodium burning; core catcher material interactions; accident release of sodium oxide aerosol; and LMFBR risk assessment

  11. Major Oil Plays in Utah and Vicinity. Quarterly Technical Progress Report

    International Nuclear Information System (INIS)

    Thomas C. Chidsey; Craig D. Morgan; Kevin McClure; Douglas A. Sprinkel; Roger L. Bon; Hellmut H. Doelling

    2003-01-01

    Utah oil fields have produced over 1.2 billion barrels (191 million m 3 ). However, the 13.7 million barrels (2.2 million m 3 ) of production in 2002 was the lowest level in over 40 years and continued the steady decline that began in the mid-1980s. The Utah Geological Survey believes this trend can be reversed by providing play portfolios for the major oil-producing provinces (Paradox Basin, Uinta Basin, and thrust belt) in Utah and adjacent areas in Colorado and Wyoming. Oil plays are geographic areas with petroleum potential caused by favorable combinations of source rock, migration paths, reservoir rock characteristics, and other factors. The play portfolios will include: descriptions and maps of the major oil plays by reservoir; production and reservoir data; case-study field evaluations; locations of major oil pipelines; identification and discussion of land-use constraints; descriptions of reservoir outcrop analogs; and summaries of the state-of-the-art drilling, completion, and secondary/tertiary techniques for each play. This report covers research activities for the sixth quarter of the project (October 1 through December 31, 2003). This work included describing outcrop analogs for the Jurassic Twin Creek Limestone and Mississippian Leadville Limestone, major oil producers in the thrust belt and Paradox Basin, respectively, and analyzing best practices used in the southern Green River Formation play of the Uinta Basin. Production-scale outcrop analogs provide an excellent view of reservoir petrophysics, facies characteristics, and boundaries contributing to the overall heterogeneity of reservoir rocks. They can be used as a ''template'' for evaluation of data from conventional core, geophysical and petrophysical logs, and seismic surveys. In the Utah/Wyoming thrust belt province, the Jurassic Twin Creek Limestone produces from subsidiary closures along major ramp anticlines where the low-porosity limestone beds are extensively fractured and sealed by

  12. The Agency's Technical Co-operation programme with Guatemala, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $3 million of Agency support received, Guatemala ranks 46th among all recipients of technical assistance in the period 1958 - 1991. Almost three quarters of the assistance during the past ten years has been provided in the form of equipment (72%), followed by training (15%) and expert services (13%). Seventy-eight per cent of the resources were provided by the Technical Assistance and Co-operation Fund, the rest was made available through extrabudgetary contributions (21%) and assistance in kind (1%). With regard to project disbursement by sector, the largest areas have been nuclear physics and chemistry (37%), agriculture (28%), nuclear medicine (16%) and hydrology (8%). The remaining 11% were shared by general atomic energy development, nuclear raw materials, nuclear engineering and technology, and nuclear safety

  13. The Agency's Technical Co-operation programme with Zaire, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $3.9 million of Agency support received, Zaire ranks 38th among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (60%), followed by training (24%) and expert services (16%). With a share of 76%, the Technical Assistance and Co-operation Fund has provided more than three quarters of the total resources available, while only small shares were made available through UNDP (11%), extrabudgetary contributions (4%) and assistance in kind (9%). With regard to project disbursements during the past ten years, by sector, the largest area has been general atomic energy development (26%), followed by agriculture (18%), nuclear safety (18%), nuclear techniques in industry and hydrology (13%), and nuclear physics and chemistry (11%)

  14. Composite quarterly technical report: long-term high-level waste technology, October-December 1980

    International Nuclear Information System (INIS)

    Cornman, W.R.

    1981-04-01

    The technical information in this report summarizes work performed at participating sites to immobilize high-level radioactive wastes. The areas reported are in: program management and support; waste preparation; waste fixation; and final handling. Majority of the studies were in the area of waste fixation, some of which are: leaching tests of ceramic forms, high silica glass, graphite powder and other carbon preparations; viscosity measurements for a range of waste-glass compositions from references borosilicate glass to high-alumina glasses; neutron activation analysis for measuring leach rates; preparation of SYNROC D spheres; formulations for preparing ceramics from defense waste composition; development of a pilot-scale glass melter, and kinetic studies of slag formation in glass melters

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

    Energy Technology Data Exchange (ETDEWEB)

    Francfort, J.; Bassett, R.R.; Briasco, S. [and others

    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.

  16. Flue gas conditioning for improved particle collection in electrostatic precipitators. Quarterly technical report

    Energy Technology Data Exchange (ETDEWEB)

    Durham, M.D.

    1992-04-27

    The purpose of this research program is to identify and evaluate a variety of additives capable of increasing particle cohesion which could be used for improving collection efficiency in an ESP. A three-phase screening process will be used to provide the, evaluation of many additives in a logical and cost-effective manner. The three step approach involves the following experimental setups: 1. Provide a preliminary screening in the laboratory by measuring the effects of various conditioning agents on reentrainment of flyash particles in an electric field operating at simulated flue gas conditions. 2. Evaluate the successful additives using a 100 acfm bench-scale ESP operating on actual flue gas. 3. Obtain the data required for scaling up the technology by testing the two or three most promising conditioning agents at the pilot scale.

  17. Technical Co-operation between developing countries

    International Nuclear Information System (INIS)

    2001-01-01

    In the plan of activities of the project Int/0/060 Technical Cooperation Between Developing Countries a Workshop on Public Awareness Promotional Literature was included with the purpose of preparing public and professional awareness literature and to develop a strategy which would enable Tissue Banks to present their mission to their public,professional health workers and clinical users.To identify the information to be provided to potential donors about the value of the donation.To prepare instructions to be given to potential users about the various types of grafts available.To develop a strategy wi ch would enable Tissue Banks to present themselves to their public and tissue users

  18. Quantum operations: technical or fundamental challenge?

    International Nuclear Information System (INIS)

    Mielnik, Bogdan

    2013-01-01

    A class of unitary operations generated by idealized, semiclassical fields is studied. The operations implemented by sharp potential kicks are revisited and the possibility of performing them by softly varying external fields is examined. The possibility of using the ion traps as ‘operation factories’ transforming quantum states is discussed. The non-perturbative algorithms indicate that the results of abstract δ-pulses of oscillator potentials can become real. Some of them, if empirically achieved, could be essential to examine certain atypical quantum ideas. In particular, simple dynamical manipulations might contribute to the Aharonov–Bohm criticism of the time–energy uncertainty principle, while some others may verify the existence of fundamental precision limits of the position measurements or the reality of ‘non-commutative geometries’. (paper)

  19. INEL oversight program. Quarterly technical progress report, January 1993--December 1993

    International Nuclear Information System (INIS)

    1994-01-01

    Idaho's successful lawsuit over shipments of spent nuclear fuel is a major milestone for 1993. The challenge forced the U.S. Department of Energy to cease all shipments of spent nuclear fuel to the Idaho National Engineering Laboratory until a site-wide environmental impact statement is completed. This agreement is a significant victory in Idaho's battle to hold the federal government responsible for its actions and force compliance with applicable laws. Much of the State's INEL-related activity in 1993 focused on ensuring that INEL operations are conducted in a manner that protects public health and the environment

  20. Biochemical removal of HAP precursors from coal. Quarterly technical progress report, April--June 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    Analytical methods were finalized and all analyses completed on shake flask tests with Indiana No. 5 and Pittsburgh No. 8 coal. A column leaching-rotating biological contractor (RBC) unit was used to bioleach pyrite and hazardous air pollutant precursors from Pittsburgh No. 8 coal. Shake flask tests with Rosebud subbituminous coal were begun. In connection with upcoming slurry column reactor tests, coal was prepared and shipped to INEL, and a detailed work plan was developed for operation and sampling for the tests. A manuscript and poster was prepared for presentation at the PETC contractors conference.

  1. Technical co-operation for nuclear safety in developing countries

    International Nuclear Information System (INIS)

    Flakus, F.N.; Giuliani, P.

    1984-01-01

    The Agency's programme on technical co-operation for nuclear safety is, largely, responsive in character and the Agency's response is tailored to needs identified by developing countries. However, the Agency's assistance alone is not sufficient: technical co-operation can only be successful and is most effective when there is also a strong input from the counterpart body participating in a particular project. The commitment of national governments is fundamental to success. Technical co-operation is most fruitful if the Agency's assistance capabilities and the recipient country's co-operation capabilities match. Co-operation activities mostly take the form of single projects hosted by individual institutions within a single country; regional and inter-regional projects are also important

  2. Advanced direct liquefaction concepts for PETC generic units. Quarterly technical progress report, January--March 1992

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-01

    In the Advance Coal Liquefaction Concept Proposal (ACLCP) carbon monoxide (CO) and water have been proposed as the primary reagents in the pretreatment process. The main objective of this project is to develop a methodology for pretreating coal under mild conditions based on a combination of existing processes which have shown great promise in liquefaction, extraction and pyrolysis studies. The aim of this pretreatment process is to partially depolymerise the coal, eliminate oxygen and diminish the propensity for retograde reactions during subsequent liquefaction. The desirable outcome of the CO pretreatment step should be: (1) enhanced liquefaction activity and/or selectivity toward products of higher quality due to chemical modification of the coal structure; (2) cleaner downstream products; (3) overall improvement in operability and process economics.

  3. Technical and organizational support for the operator

    International Nuclear Information System (INIS)

    Harrison, J.R.; Prescott, W.

    1981-01-01

    The requirement for staff and facilities on- and off-site to provide technical support to the plant personnel in normal and under accident conditions has been highlighted over the past 18 months as part of the post-TMI investigations. In the Central Electricity Generating Board (CEGB) considerable attention has always been paid to these requirements but naturally the experience of TMI has led to a review of the existing arrangements to determine whether any improvements and modifications were advisable. Similarly, the CEGB has always paid particular attention to the development of an appropriate emergency plant covering both the on-site damage control activities and off-site evacuation procedures consistent with the demography of the particular site being considered. An important aspect of gaining confidence in the potential success of the emergency plan is the regular practice and exercising of individual parts of the plan and its totality, and full attention is given also to these aspects. The paper reviews in some detail the ways in which the CEGB has met the requirements for the different aspects enumerated above, and will trace the approaches which have developed in the training and practices in respect of accident procedures. (author)

  4. Accreditation Council for Graduate Medical Education (ACGME) Surgery Resident Operative Logs: The Last Quarter Century.

    Science.gov (United States)

    Drake, Frederick Thurston; Aarabi, Shahram; Garland, Brandon T; Huntington, Ciara R; McAteer, Jarod P; Richards, Morgan K; Zern, Nicole Kansier; Gow, Kenneth W

    2017-05-01

    To describe secular trends in operative experience for surgical trainees across an extended period using the most comprehensive data available, the Accreditation Council for Graduate Medical Education (ACGME) case logs. Some experts have expressed concern that current trainees are inadequately prepared for independent practice. One frequently mentioned factor is whether duty hours' restrictions (DHR) implemented in 2003 and 2004 contributed by reducing time spent in the operating room. A dataset was generated from annual ACGME reports. Operative volume for total major cases (TMC), defined categories, and four index laparoscopic procedures was evaluated. TMC dropped after implementation of DHR but rebounded after a transition period (949 vs 946 cases, P = nonsignificance). Abdominal cases increased from 22% of overall cases to 31%. Alimentary cases increased from 21% to 26%. Trauma and vascular surgery substantially decreased. For trauma, this drop took place well before DHR. The decrease in vascular surgery also began before DHR but continued afterward as well: 148 cases/resident in the late 1990s to 107 currently. Although total operative volume rebounded after implementation of DHR, diversity of operative experienced narrowed. The combined increase in alimentary and abdominal cases is nearly 13%, over a half-year's worth of operating in 5-year training programs. Bedrock general surgery cases-trauma, vascular, pediatrics, and breast-decreased. Laparoscopic operations have steadily increased. If the competence of current graduates has, in fact, diminished. Our analysis suggests that operative volume is not the problem. Rather, changing disease processes, subspecialization, reductions in resident autonomy, and technical innovation challenge how today's general surgeons are trained.

  5. The JMTR operation and technical development, 3

    International Nuclear Information System (INIS)

    1989-10-01

    The JMTR complex consists of a 50MW high neutron flux reactor (JMTR; Japan Materials Testing Reactor), the irradiation facilities, a hot laboratory and a nuclear critical assembly (JMTRC; Japan Materials Testing Reactor Critical Assembly). Many irradiation examinations have been carried out by the capsules, hydraulic rabbits and loop facilities in the JMTR since 1971 when 50MW high power operation was attained. These irradiation facilities and any post irradiation examination equipments have been fabricated, modified and replaced to meet the needs of the times. And now, one gas loop (OGL-1; Oarai Gas Loop-1), two water loops (OWL-2; Oarai Water Loop-2, OSF-1; Oarai Shround Facility-1), two hydraulic rabbits and any capsules are in the JMTR. This report describes the activities of the JMTR project performed in fiscal year 1986∼1988 as following; 1) the operations and maintenances of the JMTR complex, 2) fabrication of the operation backup systems of the reactor and irradiation facilities, 3) JMTR driver fuel enrichment reduce program, 4) the fabrications, modifications and replacements of the irradiation facilities and reactor core components, 5) any irradiation tests by the capsules, 6) developments of the irradiation techniques and post irradiation examination techniques, 7) the fundamental studies to conduct irradiation techniques, 8) future program in the JMTR. (author)

  6. Power systems development facility. Quarterly technical progress report, July 1, 1994--September 30, 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

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

  7. MHD Integrated Topping Cycle Project. Thirteenth quarterly technical progress report, August 1, 1990--October 31, 1990

    Energy Technology Data Exchange (ETDEWEB)

    1992-01-01

    The overall objective of the project is to design and construct prototypical hardware for an integrated MHD topping cycle, and conduct long duration proof-of-concept tests of integrated system at the US DOE Component Development and Integration Facility in Butte, Montana. The results of the long duration tests will augment the existing engineering design data base on MHD power train reliability, availability, maintainability, and performance, and will serve as a basis for scaling up the topping cycle design to the next level of development, an early commercial scale power plant retrofit. The components of the MHD power train to be designed, fabricated, and tested include: A slagging coal combustor with a rated capacity of 50 MW thermal input, capable of operation with an Eastern (Illinois {number_sign}6) or Western (Montana Rosebud) coal, a segmented supersonic nozzle, a supersonic MHD channel capable of generating at least 1.5 MW of electrical power, a segmented supersonic diffuser section to interface the channel with existing facility quench and exhaust systems, a complete set of current control circuits for local diagonal current control along the channel, and a set of current consolidation circuits to interface the channel with the existing facility inverter.

  8. Proton resonance spectroscopy. Quarterly technical progress report, December 1992--November 1995

    International Nuclear Information System (INIS)

    Shriner, J.F. Jr.

    1995-11-01

    Work on chaos in the low-lying levels of nuclei has continued on several fronts. The major effort has been study of the 29 Si(p,γ) reaction with the goal of establishing a complete level scheme for 30 P and analyzing the eigenvalue fluctuations for evidence of chaos. These measurements are in progress, and the current status is described. A related topic is the search for different signatures of chaos which do not require the extremely high degree of completeness and purity necessary for eigenvalue analyses; those efforts are discussed in Sections 2 and 3. The possibility of studying both parity violation and time-reversal invariance violation with charged particle resonances has been explored by performing calculations using experimentally measured resonance parameters. Large enhancements are indeed available; the results are discussed in Sections 4 and 5. Preparations for an experimental study of parity violation using these techniques are ongoing. An undergraduate project searching for experimental evidence of a parity dependence of level density is discussed in Section 6. A number of improvements to the operation of the TUNL KN accelerator have been implemented in the past three years. These are described in Section 7

  9. Proton resonance spectroscopy. Quarterly technical progress report, December 1992--November 1995

    Energy Technology Data Exchange (ETDEWEB)

    Shriner, J.F. Jr.

    1995-11-01

    Work on chaos in the low-lying levels of nuclei has continued on several fronts. The major effort has been study of the {sup 29}Si(p,{gamma}) reaction with the goal of establishing a complete level scheme for {sup 30}P and analyzing the eigenvalue fluctuations for evidence of chaos. These measurements are in progress, and the current status is described. A related topic is the search for different signatures of chaos which do not require the extremely high degree of completeness and purity necessary for eigenvalue analyses; those efforts are discussed in Sections 2 and 3. The possibility of studying both parity violation and time-reversal invariance violation with charged particle resonances has been explored by performing calculations using experimentally measured resonance parameters. Large enhancements are indeed available; the results are discussed in Sections 4 and 5. Preparations for an experimental study of parity violation using these techniques are ongoing. An undergraduate project searching for experimental evidence of a parity dependence of level density is discussed in Section 6. A number of improvements to the operation of the TUNL KN accelerator have been implemented in the past three years. These are described in Section 7.

  10. The JMTR operation and technical development, 4

    International Nuclear Information System (INIS)

    1990-11-01

    The JMTR complex consists of a 50 MW high neutron flux reactor (JMTR; Japan Materials Testing Reactor), the irradiation facilities, a hot laboratory and nuclear critical assembly (JMTRC; Japan Materials Testing Reactor Critical Assembly). Many irradiation examination have been carried out by the capsules, hydraulic rabbit and loop facilities in the JMTR since 1971 when 50 MW high power operation started. These irradiation facilities have been fabricated, modified and replaced according to the needs of the times. And now, one high temperature gas loop (OGL-1, Oarai Gas Loop-1), two water loop (OWL-2; Oarai Water Loop-2, OSF-1; Oarai Shroud Facility), two hydraulic rabbit facilities and many capsules are in the JMTR. And post irradiation examination equipments have been developed according to the needs. This report describes the activities of JMTR Project performed in fiscal year 1989 as following; 1) The operation and management of the JMTR, Hot Laboratory and the JMTRC, 2) utilization status of the JMTR, 3) conversion to Low Enrichment Uranium Fuel, 4) fabrication, modification and replacement of the irradiation facilities and reactor core components, 5) development of the irradiation techniques and post irradiation examination techniques, 6) the fundamental studies to conduct irradiation techniques, 7) future program of the JMTR. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  12. The Agency's technical co-operation activities in 1992

    International Nuclear Information System (INIS)

    1993-08-01

    This report on the International Atomic Energy Agency's Technical Co-operation Activities in 1992 contains an overview of the general issues involved, including both in-house and external developments, resources and delivery, and evaluation of programs; an overview by field of activity and by division within the Agency; an overview by geographic area, distinguishing (i) Africa, (ii) Asia and the Pacific, (iii) Latin America, (iv) and the Middle East and Europe; an overview by component (i.e., experts, equipment, fellowships, training courses, sub-contracts and miscellaneous); and an overview by fund technical assistance and co-operation fund, extrabudgetary resources, United Nations Development Program (UNDP), assistance in kind. It also contains a profile on technical co-operation activities in Latin America. Projects concluded during 1992 are listed together with a description of their achievements. It concludes with implementation summaries. 10 figs, 9 tabs

  13. Thin film polycrystalline silicon solar cells. Quarterly technical progress report No. 3, 1 April 1980-30 June 1980

    Energy Technology Data Exchange (ETDEWEB)

    Sarma, K. R.; Rice, M. J.; Legge, R.; Ellis, R. J.

    1980-06-01

    During this third quarter of the program, the high pressure plasma (hpp) deposition process has been thoroughly evaluated using SiHCl/sub 3/ and SiCl/sub 4/ silicon source gases, by the gas chromatographic analysis of the effluent gases from the reactor. Both the deposition efficiency and reactor throughput rate were found to be consistently higher for hpp mode of operation compared to conventional CVD mode. The figure of merit for various chlorosilanes as a silicon source gas for hpp deposition is discussed. A new continuous silicon film deposition scheme is developed, and system design is initiated. This new system employs gas interlocks and eliminates the need for gas curtains which have been found to be problematic. Solar cells (2 cm x 2 cm area) with AM1 efficiencies of up to 12% were fabricated on RTR grain enhanced hpp deposited films. The parameters of a 12% cell under simulated AM1 illumination were: V/sub OC/ = 0.582 volts, J/sub SC/ = 28.3 mA/cm/sup 2/ and F.F. = 73.0%.

  14. Predicting technology operational availability using technical maturity assessment

    International Nuclear Information System (INIS)

    Kenley, C.R.; Creque, T.R.

    1998-01-01

    A technical maturity assessment method was performed by systems engineers in collaboration with an advisory panel composed of team members from different Department of Energy sites and from different engineering and science disciplines. Various stabilization technologies were assessed annually as to their relative maturity and availability for use in stabilizing nuclear materials. After three years of assessments, several of the technologies are now components of operational systems. A regression analysis of the historical assessments was performed, and it was concluded that the numerical technical maturity score produced by a team of experts can provide a powerful predictor of the time remaining until the operational application of technologies

  15. Training of technical staff for nuclear power station operation

    International Nuclear Information System (INIS)

    Haire, T.P.; Myerscough, P.B.

    1981-01-01

    The statutory training requirements covering the technical staff in the CEGB (Central Electricity Generating Board) are discussed. Details of the training programmes emphasize the importance of the staff having a thorough understanding of the nuclear processes involved in the station operation and not relying solely upon a mechanistic approach to operating procedures. The impact of this philosophy on the design of training simulators is examined and a brief comparison is made with the training philosophies in other countries. (U.K.)

  16. RF Regional Technical Centers for MPC and A Sustainability Operations

    International Nuclear Information System (INIS)

    Lambert, L D; Toth, W J; Hendrickson, S

    2004-01-01

    The National Nuclear Security Administration (NNSA) programmatic vision to be a catalyst in Russia's assumption of responsibility for long-term system operation is exemplified in the sustainability cooperation with the RF Ministry of Defense (MOD). An identified goal for the MPC and A Program is to encourage the development of Russian Federation (RF) capabilities and commitments to operate and maintain safeguard improvements. The RF MOD Technical Support Center development fulfills the NNSA mission and MPC and A Program goal. The regional technical center concept involves a systematic approach to aid in the determination of the level of sustainability assistance required to transition operators, maintenance, training, and testing of MPC and A systems to the RF MOD. This paper describes the process used to create the RF MOD Technical support center. First are described the needs analyses conducted to determine the key system sustainability factors requiring support. These sustainability functions are then compiled to influence the form and ultimate physical design of the technical support center. Operational interfaces are described, in detail that show the benefit of the center to the individual sites. Finally, benefits relating to information accessibility and other economies of scale are described that highlight the central center concept's strengths

  17. 78 FR 1823 - Cable Television Technical and Operational Requirements

    Science.gov (United States)

    2013-01-09

    ... FEDERAL COMMUNICATIONS COMMISSION 47 CFR Part 79 [MB Docket No. 12-217; DA 12-2081] Cable Television Technical and Operational Requirements AGENCY: Federal Communications Commission. ACTION: Proposed rule; extension of reply comment period. SUMMARY: In this document, the Commission extends the deadline...

  18. Turnaround operations analysis for OTV. Volume 2: Detailed technical report

    Science.gov (United States)

    1988-01-01

    The objectives and accomplishments were to adapt and apply the newly created database of Shuttle/Centaur ground operations. Previously defined turnaround operations analyses were to be updated for ground-based OTVs (GBOTVs) and space-based OTVs (SBOTVs), design requirements identified for both OTV and Space Station accommodations hardware, turnaround operations costs estimated, and a technology development plan generated to develop the required capabilities. Technical and programmatic data were provided for NASA pertinent to OTV round and space operations requirements, turnaround operations, task descriptions, timelines and manpower requirements, OTV modular design and booster and Space Station interface requirements. SBOTV accommodations development schedule, cost and turnaround operations requirements, and a technology development plan for ground and space operations and space-based accommodations facilities and support equipment. Significant conclusion are discussed.

  19. Independent technical review of the Hanford Tank Farm Operations

    International Nuclear Information System (INIS)

    1992-07-01

    The Independent Technical Assessment of the Hanford Tank Farm Operations was commissioned by the Assistant Secretary for Environmental Restoration and Waste Management on November 1, 1991. The Independent Technical Assessment team conducted on-site interviews and inspections during the following periods: November 18 to 22,1991; April 13 to 17; and April 27 to May 1, 1992. Westinghouse Hanford Company is the management and operating contractor for the Department of Energy at the Hanford site. The Hanford Tank Farm Operations consists of 177 underground storage tanks containing 61 million gallons of high-level radioactive mixed wastes from the chemical reprocessing of nuclear fuel. The Tank Farm Operations also includes associated transfer lines, ancillary equipment, and instrumentation. The Independent Technical Assessment of the Hanford Tank Farm Operations builds upon the prior assessments of the Hanford Waste Vitrification System and the Hanford Site Tank Waste Disposal Strategy.The objective of this technical assessment was to determine whether an integrated and sound program exists to manage the tank-waste storage and tankfarm operations consistent with the Assistant Secretary for Environmental Restoration and Waste Management's guidance of overall risk minimization. The scope of this review includes the organization, management, operation, planning, facilities, and mitigation of the safety-concerns of the Hanford Tank Waste Remediation System. The assessments presented in the body of this report are based on the detailed observations discussed in the appendices. When the assessments use the term ''Hanford'' as an organizational body it means DOE-RL and Westinghouse Hanford Company as a minimum, and in many instances all of the stake holders for the Hanford site

  20. BX in-situ oil-shale project. Quarterly technical progress report, June 1, 1981-August 31, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Dougan, P.M.

    1981-09-20

    June 1, 1981-August 31, 1981 was the third consecutive quarter of superheated steam injection at the BX In Situ Oil Shale Project. Injection was continuous except for the period of July 14th to August 1st when the injection was suspended during the drilling of core hole BX-37. During the quarter, 99,760 barrels of water as superheated steam were injected into Project injection wells at an average well head temperature of 752/sup 0/F and an average wellhead pressure of 1312 PSIG. During the same period, 135,469 barrels of fluid were produced from the Project production wells for a produced to injected fluid ratio of 1.36 to 1.0. Net oil production during the quarter was 38 barrels.

  1. Technical information report: Plasma melter operation, reliability, and maintenance analysis

    International Nuclear Information System (INIS)

    Hendrickson, D.W.

    1995-01-01

    This document provides a technical report of operability, reliability, and maintenance of a plasma melter for low-level waste vitrification, in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. A process description is provided that minimizes maintenance and downtime and includes material and energy balances, equipment sizes and arrangement, startup/operation/maintence/shutdown cycle descriptions, and basis for scale-up to a 200 metric ton/day production facility. Operational requirements are provided including utilities, feeds, labor, and maintenance. Equipment reliability estimates and maintenance requirements are provided which includes a list of failure modes, responses, and consequences

  2. Operating experience feedback report: Technical specifications: Commercial power reactors

    International Nuclear Information System (INIS)

    O'Reilly, P.D.; Plumlee, G.L. III.

    1989-03-01

    This report documents a trends and patterns analysis of technical specification (TS)-related licensee event reports (LERs) conducted by the Nuclear Regulatory Commission's (NRC's) Office for Analysis and Evaluation of Operational Data (AEOD). The objectives of this analysis were (1) to identify and catalog technical specification-related LERs, (2) to categorize and evaluate the events reported in these a LERs, (3) to identify any issues arising from the evaluation which appear to have generic safety significance, or which relate to the on-going Technical Specification Improvement Program, and (4) to trend the results obtained from the analysis of the data obtained in (1) through (3). 9 refs., 9 figs., 22 tabs

  3. Ergonomic requirements for the operation of machines and technical equipment

    Directory of Open Access Journals (Sweden)

    Górny Adam

    2017-01-01

    Full Text Available In order to operate machinery and equipment safely, it is critical for the solutions in place to conform to design-related and operating requirements. Design-related requirements are primarily the responsibility of machine designers/developers and manufacturers. Operating requirements should be satisfied by employers, who are responsible for ensuring safe working conditions for their employees. Under applicable laws, machinery and equipment should be designed, produced and then operated without placing excessive loads on workers and in keeping with machine functionality and intended use. One should also ensure that machinery and equipment can be maintained and adjusted without exposing their operators to hazards. Ergonomic criteria are an integral part of such requirements. They ensure that human users and operators of technical equipment are enabled to function properly. Design-related requirements are viewed as a priority safety consideration. While they facilitate the use of technical tools, the actual safety of employees ultimately depends on the satisfaction of specific requirements during operation.

  4. Support of enhanced oil recovery to independent producers in Texas. Quarterly technical progress report, July 1, 1995--September 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Fotouh, K.H.

    1995-09-30

    The main objective of this project is to support independent oil producers in Texas and to improve the productivity of marginal wells utilizing enhanced oil recovery techniques. The main task carried out this quarter was the generation of an electronic data base.

  5. Evaluation of using cyclocranes to support drilling and production of oil and gas in wetland areas. Third quarterly technical progress report, First quarter, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Eggington, W.J.

    1993-06-01

    The planned program falls under wetlands area research related to drilling, production, and transportation of oil and gas resources. Specifically the planned program addresses an evaluation of using cyclocraft to transport drill rigs, mud, pipes and other materials and equipment in a cost effective and environmentally safe manner to support oil and gas drilling and production operations in wetland areas. The cyclocraft is a proven hybrid aircraft that utilizes aerostatic and aerodynamic lift. This type of aircraft has considerable payload capacity, VTOL capability, high controllability, low operating cost, low downwash and high safety. The benefits of using a cyclocraft to transport drill rigs and materials over environmentally-sensitive surfaces would be significant. The cyclocraft has considerable cost and operational advantages over the helicopter. The major activity during the report period was focussed on Task 4, Preliminary Design. The selected design has been designated H.1 Cyclocraft by MRC. The preliminary design work was based on the results of the three preceding tasks. A report was initiated that contains descriptions of the H.1 Cyclocraft and its subsystems; options available for the final aircraft design process; performance, geometry, weights and power data; logistics and considerations relating to cyclocraft operations in wetlands.

  6. 200-UP-2 Operable Unit technical baseline report

    International Nuclear Information System (INIS)

    Deford, D.H.

    1991-02-01

    This report is prepared in support of the development of a Remedial Investigation/Feasibility Study (RI/FS) Work Plan for the 200-UP-2 Operable Unit by EBASCO Environmental, Incorporated. It provides a technical baseline of the 200-UP-2 Operable Unit and results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (Westinghouse Hanford). The 200-UP-2 Operable Unit Technical Baseline Report is based on review and evaluation of numerous Hanford Site current and historical reports, Hanford Site drawings and photographs and is supplemented with Hanford Site inspections and employee interviews. No field investigations or sampling were conducted. Each waste site in the 200-UP-2 Operable Unit is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. The 200-UP-2 Operable Unit consists of liquid-waste disposal sites in the vicinity of, and related to, U Plant operations in the 200 West Area of the Hanford Site. The ''U Plant'' refers to the 221-U Process Canyon Building, a chemical separations facility constructed during World War 2. It also includes the Uranium Oxide (UO 3 ) Plant, which was constructed at the same time and, like the 221-U Process Canyon Building, was later converted for other missions. Waste sites in the 200-UP-2 Operable Unit are associated with the U Plant Uranium Metal Recovery Program mission that occurred between 1952 and 1958 and the UO 3 Plant's ongoing uranium oxide mission and include one or more cribs, reverse wells, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, waste vaults, and the lines and encasements that connect them. 11 refs., 1 tab

  7. IAEA technical co-operation activities in the 1990s

    International Nuclear Information System (INIS)

    1995-01-01

    The desire to extend the many benefits of the peaceful uses of nuclear technology to all countries led as long ago as 1957 to the establishment of the IAEA and to immediate introduction of a technical co-operation programme. In the more than thirty years that have passed since that time, the potential applications of nuclear techniques have greatly expanded. Over the period, many of the applications have moved from research laboratories into hospitals, farms and industrial enterprises. The direct resources made available to the IAEA by its Member States to support technology transfer processes have grown rapidly since the late 1950s. The current trends in the technical co-operation activities of the IAEA and some examples of projects supported by the IAEA are briefly presented in this document

  8. IAEA technical co-operation and the NPT

    International Nuclear Information System (INIS)

    Velez Ocon, C.

    1985-01-01

    The IAEA technical co-operation programme promotes nuclear techniques and technologies in the developing countries. The Statute, the NPT, and the Revised Guiding Principles all reflect the desire of countries to foster an international climate where it will be unacceptable for a non-nuclear-weapon State to indulge in the development of military nuclear technology and reprehensible for States possessing this technology to offer it to others

  9. Technical aspects of ageing for long-term operation

    International Nuclear Information System (INIS)

    2003-01-01

    The aspects of plant ageing management gained increasing attention over the last ten years. Numerous technical studies have been performed to study the impact of ageing mechanisms on the safe and reliable operation of nuclear power plants. National research activities have been initiated or are in progress to provide the technical basis for decision making processes. The long-term operation of nuclear power plants is influenced by economic considerations, the socio-economic environment including public acceptance, developments in research and the regulatory framework, the availability of technical infrastructure to maintain and service the systems, structures and components as well as qualified personnel. This document restricts itself to the technical aspects of the basis for long-term operation. Its objective is the characterisation of technical key items. Regulatory aspects are being discussed within CNRA. The light water reactor (LWR) nuclear power plants in operation are generically of pressurised water reactor (PWR) or boiling water reactor (BWR) type. The design principles of the nuclear steam supply system (NSSS) are proven in long-term operation as well as the principles being applied to the balance of plant (BOP), although a rather large variety of technical solutions do exist. The steps in the developments were tremendous in the 60's and 70's up to a power output of 1200 MWe followed by a period of further optimisation in the 80's and 90's, which raised it close to 1500 MWe. The NPPs in operation can be grouped into different generations of design in order to characterise similarities in technical principles and manufacturing standards. In the area of civil and mechanical structures and components there has been continuous development to optimise the design, the materials used as well as the manufacturing technology. The majority of these structures and components is still in use. In principle there are no major obstacles to further use of these

  10. 200-BP-5 operable unit Technical Baseline report

    International Nuclear Information System (INIS)

    Jacques, I.D.; Kent, S.K.

    1991-10-01

    This report supports development of a remedial investigation/feasibility study work plan for the 200-BP-5 operable unit. The report summarizes baseline information for waste sites and unplanned release sites located in the 200-BP-5 operable unit. The sites were investigated by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (Westinghouse Hanford). The investigation consisted of review and evaluation of current and historical Hanford Site reports, drawings, and photographs, and was supplemented with recent inspections of the Hanford Site and employee interviews. No field investigations or sampling were conducted

  11. Technical Issues Map for the NHI System Interface and Support Systems Area: 1st Quarter FY 07

    International Nuclear Information System (INIS)

    Steven R. Sherman

    2006-01-01

    This document provides a mapping of technical issues associated with development of the Next Generation Nuclear Plant (NGNP) intermediate heat transport loop and nuclear hydrogen plant support systems to the work that has been accomplished or is currently underway. The technical issues are ranked according to priority and by assumed resolution dates. Due to funding limitations, not all high-priority technical issues are under study at the present time, and more resources will need to be dedicated to tackling such issues in the future. This technical issues map is useful for understanding the relative importance of various technical challenges and will be used as a planning tool for future work package planning

  12. Technical Issues Map for the NHI System Interface and Support Systems Area: 3rd Quarter FY 07

    International Nuclear Information System (INIS)

    Steven R. Sherman

    2007-01-01

    This document provides a mapping of technical issues associated with development of the Next Generation Nuclear Plant (NGNP) intermediate heat transport loop and nuclear hydrogen plant support systems to the work that has been accomplished or is currently underway. The technical issues are ranked according to priority and by assumed resolution dates. Due to funding limitations, not all high-priority technical issues are under study at the present time, and more resources will need to be dedicated to tackling such issues in the future. This technical issues map is useful for understanding the relative importance of various technical challenges and will be used as a planning tool by the NHI technical leadership for future work package planning. The technical map in its present form will be discontinued in FY08 and will be folded into a larger NHI System Interface and Support Systems project management plan and scope baseline statement in FY08

  13. The Agency's Technical Co-operation programme with Cuba, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With almost $8.2 million of Agency support received, Cuba ranks 19th among all recipients of technical assistance in the period 1958 - 1991, whereby it ranked as high as 3rd in 1982 and 4th in 1984. Over three quarters of the assistance during the past ten years has been provided in the form of equipment (81%), followed by expert services (10%) and training (9%). Seventy-one per cent of the resources were made available through the Technical Assistance and Co-operation Fund, while 28% of the resources were provided by UNDP. The remaining 1% was made available through extrabudgetary and in-kind contributions. With regard to project disbursements by sector, the largest areas have been general atomic energy development (36%), agriculture (20%), nuclear physics and chemistry (10%) and nuclear safety (10%). Industry and hydrology, nuclear engineering and technology, and nuclear medicine have each received less than ten per cent of the assistance provided

  14. Outlook for the IAEA's technical co-operation programme

    International Nuclear Information System (INIS)

    Samiei, Massoud

    1998-01-01

    This is a slide presentation dealing with the following subjects: - the IAEA's programmes; - the technical co-operation programme; - past trends in the TC programme; - new initiatives in TC; - TC programme profile; - perspectives for the future. The major programmes conducted by IAEA are concerning: - nuclear power and fuel cycle; - nuclear applications; - nuclear, radiation and waste safety, nuclear verification and security material; - management of technical co-operation; - policy making, coordination and support. In relation with the IAEA role in development process the author presents the legal framework for TC, the programme structure, and programme areas, resources, budgets, cycle, approval and implementation. Two plots regarding the recipients with and without NPP's are displayed for the period 1980-1994. Also, according to the status of the member states (without and with nuclear power programme) the programme priorities are presented. For the first case these are: radiation and waste safety, food and agriculture, water resources management human health and nutrition, human resources development, environmental protection and industrial applications. For the second case there are mentioned: radiation and nuclear safety, nuclear power operation and maintenance management, radioactive waste management, environment protection and sustainable energy options. Concerning the regional distribution the following figures are given for 1997: West Asia, 9%; Europe, 18%; Inter-regional, 11%; Africa, 24%; Latin America, 21%; East Asia and Pacific, 17%. In conclusion, the hope is expressed that the value of Technical Co-operation Programme would be seen not only in the successful transfer of technology but also, in the way that the nuclear technologies may satisfy demands for sustainable development by having a lasting impact on the life of the majority in a cost effective and environmentally sound manner

  15. GANIL, Technical report on operating accelerators, 1995-1996

    International Nuclear Information System (INIS)

    Bex, M.

    1998-01-01

    This report covers the years 1995-1996 and presents the GANIL accelerator operation, the machine studies, the technical developments, the safety problems, the SISSI system and the THI project. The technical developments refer to: production of multicharged metallic ions by the association of an excimer laser and an ECR source; production of multicharged metallic ions with an ECR source by the sputtering method; detection of beam losses and safety system for these losses; rotating spiraled wire; renovation or RF systems; renovation of power supplies and NMR system; upgrade of GANIL control system cluster; adaptation of the GANIL control system to the SPIRAL project and control system for NMR probe measurements. Annexes giving the experiments performed in nuclear physics and in fast ion physics are given as well as a list of the beams accelerated together with their characteristics (charged state, frequency, final energy, intensity on target). Also added is a list of publications

  16. Results of Scientific and Technical Supervision of Hydraulic Fracturing Operations

    Directory of Open Access Journals (Sweden)

    I.Kh. Makhmutov

    2017-11-01

    Full Text Available The paper presents actual results of the research conducted as part of a field pilot project which consisted in interpretation of minifrac test data and evaluation of the efficiency of the scientific and technical supervision of fracking operations. The research program involved 11 wells targeting Devonian terrigenous reservoirs. Minifrac tests in one perforation interval were performed only in seven wells, that is approximately in 64% of total well count. A reliable fracture closure estimate was obtained only in six wells (55%, beginning of pseudoradial flow was observed only in one well out of 11 wells (9%. Hence, conventional minifrac tests should be supplemented with other diagnostic injection tests. Analysis of the performance of hydraulic fracturing operations conducted according to this pilot project plan indicates that fracture modelling, and scientific and technical supervision of fracking operations performed by Hydrofrac Research Laboratory of Institute TatNIPIneft Tatneft PJSC have yielded beneficial effects, namely 1.44 times increase in oil production rates.

  17. PARAMETRIC DIAGNOSTICS OF THE CENTRIFUGAL SUPERCHARGER'S TECHNICAL CONDITION DURING OPERATION

    Directory of Open Access Journals (Sweden)

    Regina A. Khuramshina

    2017-01-01

    Full Text Available Abstract. Objectives The main aim is to develop a mathematical model of a centrifugal compressor and carry out a parametric diagnostics of a centrifugal supercharger's technical condition during operation. Methods  A model is proposed for calculating the thermodynamic properties of natural gas, reducing the parameters of a centrifugal compressor to the initial conditions and to the rotation frequency, as well as the integral indicators of the supercharger's technical state. The technical state of the gas path of the centrifugal supercharger of the compressor unit is determined by the parametric diagnostic method. Results  The software implementation of the mathematical model of centrifugal compressor is carried out using a DVIGwT PC. The analysis of calculations indicates that the model is appropriate, with the error being due to taking into account the properties of iso-butane and i-hexane, in contrast with the VNIIGAZ technique. The evaluation studies of a centrifugal compressor's state are indicative of the presence or absence of its defects. Conclusion  Among a number of the diagnostic methods for evaluating a centrifugal supercharger, the most effective is vibrodiagnostics. However, the search for malfunctions and nascent defects in the flowing part of the centrifugal compressor cannot be limited only to vibrodiagnostic data, which provides about 60% of the reliable information about the state of the gas-air tract. About 20% of the compressor's malfunctions and approximately half of the dangerous modes of the supercharger's flow-through part is detected using thermogasdynamic parametric analysis (parametric diagnostics. The main difficulty of the control over the technical state of the flow-through part of the centrifugal supercharger is in the complication of the quantitative evaluation of the processes taking place in the supercharger, which leads to problems in providing reliable diagnosis during a reasonable period of time.

  18. Regulatory and technical reports (Abstract Index Journal). Compilation for third quarter 1985, July-September. Volume 10, No. 3

    International Nuclear Information System (INIS)

    1985-10-01

    This compilation consists of bibliographic data and abstracts for the formal Regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. This compilation covers the period from July through September, 1985

  19. Nimrod operation and development quarterly report, October 1 to December 31 1975

    International Nuclear Information System (INIS)

    Gray, D.E.

    1976-03-01

    The Nimrod beam was on for High Energy Physics for 86.9% of HEP scheduled operating time. One experiment was completed, three continued through and one commenced setting-up. The statistics relating to the operation of Nimrod are presented. (author)

  20. Bench-scale testing of on-line control of column flotation using a novel analyzer. Third quarterly technical progress report, April 1, 1993--June 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-24

    This document contains the third quarterly technical progress report for PTI`s Bench-Scale Testing Project of a circuit integrating PTI`s KEN-FLOTETM Column Flotation Technology and PTI`s On-Line Quality Monitor and Control System. The twelve-month project involves installation and testing of a 200--300 lb/hr. bench-scale flotation circuit at PETC`s Coal Preparation Process Research Facility (CPPRF) for two bituminous coals (Upper Freeport and Pittsburgh No. 8 Seam Raw Coals). Figure 1 contains the project plan, as well as the approach to completing the major tasks within the twelve-month project schedule. The project is broken down into three phases, which include: Phase I -- Preparation: The preparation phase was performed principally at PTI`s Calumet offices from October through December, 1992. It involved building of the equipment and circuitry, as well as some preliminary design and equipment testing; Phase II -- ET Circuit Installation and Testing: This installation and testing phase of the project was performed at PETC`s CPPRF from January through June, 1993, and was the major focus of the project. It involved testing of the continuous 200--300 lb/hr. circuit; and Phase III -- Project Finalization: The project finalization phase is occurring from July through September, 1993, at PTI`s Calumet offices and involves finalizing analytical work and data evaluation, as well as final project reporting. This Third Quarterly Technical Progress Report principally summarizes the results from the benchscale testing with the second coal (Pittsburgh No. 8 Seam Coal), which occurred in April through June, 1993. It also contains preliminary economic evaluations that will go into the Final Report, as well as the plan for the final reporting task.

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

    Energy Technology Data Exchange (ETDEWEB)

    Francfort, J.E. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States); Bassett, R.R. [Sandia National Labs., Albuquerque, NM (United States); Briasco, S. [Los Angeles City Dept. of Water and Power, CA (United States)] [and others

    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.

  2. International co-operation through scientific and technical nuclear societies

    International Nuclear Information System (INIS)

    Manning Muntzing, L.

    1983-01-01

    As an international organization the American Nuclear Society (ANS) has played an active role in international co-operation of nuclear technology exchange since its establishment in 1954. The ANS has a membership of over 13,000 individuals, of whom approximately 1200 live overseas in forty countries. To carry out the goals of the Society, local sections have been established. Currently the ANS maintains 48 local sections in the United States of America and 8 overseas local sections in Africa, Asia, Europe and South America. The ANS also has formal agreements for co-operation with The Asociacion Argentina de Tecnologia Nuclear (AATN), the Israel Nuclear Society (INS), and the Chinese Nuclear Society (CNS). In 1977 the Japan Atomic Energy Society (JAES), the European Nuclear Society (ENS), and the ANS co-operation in sponsoring the First International Conference on Transfer of Nuclear Technology (ICONTT I) in Tehran, Iran. In 1982, the Second International Conference on Transfer of Nuclear Technology (ICONTT II), Buenos Aires, Argentina, was sponsored through the co-operation of the AATN, the ENS and the ANS. The ANS and its overseas sections sponsor the Pacific Basin Conference approximately every three years to discuss nuclear matters of concern to the countries around the Pacific Ocean. In 1981 the ANS held a Nuclear Technology Exhibit in Beijing, the People's Republic of China. In addition to meetings, the ANS is extensively involved in the co-operative exchange of applied nuclear research information through its publications. Nuclear Technology, a technical journal, is published monthly under joint ownership of the ENS and the ANS. The ANS has been a leader in voluntary standards development since 1958. In its dedication to the co-operation of international nuclear technology the ANS maintains a comprehensive international exchange of nuclear standards

  3. Occupational exposure to ambient electromagnetic fields of technical operational personnel working for a mobile telephone operator

    International Nuclear Information System (INIS)

    Chauvin, S.; Gibergues, M. L.; Wuethrich, G.; Picard, D.; Desreumaux, J. P.; Bouillet, J. C.

    2009-01-01

    In order to investigate the exposure of operational personnel to radiofrequency electromagnetic fields when working for a mobile telephone operator, exposimeters were used to make individual records on 23 Technical Operations personnel (mobile telephone maintenance staff) and also on 22 Other Workers. The exposure densities, to which each of the 45 subjects was subjected, were quantified using 229 exposure indicators. Cluster analysis techniques were applied to the data, in an attempt to show that they would re-emerge as belonging to one of the two groups, i.e. the Technical Operational Personnel group or the Other Workers group. This exploratory investigation has shown that the cluster analysis does not reveal a sufficiently reliable emergence of the two groups, even though certain exposure indicators were significantly different for the two groups. In addition, the use of a Learning Group method does not lead to the discovery of a predictive law that could identify the Technical Operational Personnel as a sub-group within the overall group. (authors)

  4. Independent Electricity Market Operator integration management participant technical reference manual

    International Nuclear Information System (INIS)

    1999-01-01

    The document provides potential participants with the essential technical information to permit them to participate in the IMO-administered markets, and is not intended to be a complete technical reference manual for all issues within the realm of electricity production, distribution, or consumption. Written for the participants, it provides only that information which is relevant to the participant for interfacing with the IMO and participating in the market. Written as a generic guide, all the information contained within it may not be relevant to all the participants. The document's intent is to provide participants with a description of the various facilities and interfaces required by market participants to take part in the IMO-administered markets. The document supplements the market rules and provides installation, set-up, and configuration information for the various tools and facilities that will be required for market participation as a supplier, carrier/delivery (transmitter/distributor), generator, or consumer in the market. Aspects considered include: participant workstation specifications, dispatch workstation specification, message exchange, remote terminal unit specification, AGC operational RTU specification, real time network connection specification, telephone connection specification, revenue administration specification, funds administration specification, data catalogues, market information, power grid connection requirements, and appendices

  5. Technical innovations at NPP Dukovany - for safe and efficient operation

    International Nuclear Information System (INIS)

    Sabata, M.; Vasa, I.

    2000-01-01

    Inherent features of the NPP Dukovany design provide a significant confidence in its nuclear safety assurance; among these features should be emphasised the reactor core stability and its control and protection system capability to hold the reactor in safe state following scram or accident conditions. Nevertheless, NPP Dukovany was designed in the early seventies, and current requirements for nuclear safety assurance are more strict and/or specific as a result of the technical development and lessons learned from nuclear accidents. The paper compares the safety design base established at the time of NPP Dukovany project implementation and the current reference design base. The paper also presents procedures applied to implement technical and operational measures which are introduced to fulfil the current basic safety criteria. The scope of such measures applied at NPP Dukovany is compared with that of EU countries introduced for the same reason - to meet the updated safety related requirements. Examples of some innovations already implemented or under implementation give an idea how NPP Dukovany proceeds in reaching the goal of harmonising its safety with the requirements to be met before the Czech Republic becomes a member country of the European Union. (author)

  6. Regulatory and technical reports (Abstract Index Journal). Compilation for first quarter 1986, January-March. Volume 11, No. 1

    International Nuclear Information System (INIS)

    1986-04-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission staff and its contractors, as well as conference proceedings. Entries are indexed by contractor report number, personal author, subject, NRC originating organization, NRC contract sponsor, contractor, and licensed facility

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

    International Nuclear Information System (INIS)

    Moore, J.P.

    2000-01-01

    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

  8. Regulatory and technical reports (abstract index journal). Compilation for third quarter 1984, July-September. Volume 9, No. 3

    International Nuclear Information System (INIS)

    1984-11-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, and NUREG/CR-XXXX. These precede the following indexes: Contractor Report Number, Personal Author, Subject, NRC Originating Organization (Staff Reports), NRC Contract Sponsor (Contractor Reports), Contractor, and Licensed Facility

  9. A quarter of a century of experience with aortic valve-sparing operations.

    Science.gov (United States)

    David, Tirone E; Feindel, Christopher M; David, Carolyn M; Manlhiot, Cedric

    2014-09-01

    To examine the late outcomes of aortic valve-sparing operations to treat patients with aortic root aneurysm with and without aortic insufficiency (AI) in a cohort of patients followed up prospectively since 1988. A total of 371 consecutive patients had undergone aortic valve-sparing surgery (mean age, 47 ± 15 years; 78% men) from 1988 through 2010. In addition to the aortic root aneurysm, 47% had moderate or severe AI, 35.5% had Marfan syndrome, 12.1% had type A aortic dissection, 9.2% had bicuspid aortic valve, 8.4% had mitral insufficiency, 16.1% had aortic arch aneurysm, and 10.2% had coronary artery disease. Reimplantation of the aortic valve was used in 296 patients and remodeling of the aortic root in 75. Cusp repair by plication of the free margin along the nodule of Arantius was used in 36.6% of patients, and reinforcement of the free margin with a double layer of fine Gore-Tex suture in 24.2%. The patients were followed up prospectively with images of the aortic root for a median follow-up of 8.9 ± 5.2 years. A total of 4 operative and 39 late deaths occurred. Survival at 18 years was 76.8% ± 4.31%, lower than that for the general population matched for age and gender. Age, type A aortic dissection, impaired ventricular function, and preoperative AI were associated with increased mortality on multivariable analysis. Reoperations on the aortic valve were performed in 8 patients for recurrent AI and in 2 for infective endocarditis. Freedom from reoperation on the aortic valve at 18 years was 94.8% ± 2.0%. No predictors of the need for reoperation were found on multivariable analysis. Eighteen patients developed AI greater than mild. Freedom from AI greater than mild at 18 years was 78.0% ± 4.8%. No predictors of recurrent AI were identified on multivariable analysis. Aortic valve-sparing operations continue to provide excellent clinical outcomes, although a slow but progressive deterioration of aortic valve function seems to occur during the first 2

  10. Atmospheric Radiation Measurement Climate Research Facility Operations Quarterly Report October 1-December 31, 2016

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-01-01

    Individual datastreams from instrumentation at the U.S. Department of Energy (DOE) Atmospheric Radiation Measurement (ARM) Climate Research Facility fixed and mobile research observatories (sites) are collected and routed to the ARM Data Center (ADC). The Data Management Facility (DMF), a component of the ADC, executes datastream processing in near-real time. Processed data are then delivered approximately daily to the ARM Data Archive, also a component of the ADC, where they are made freely available to the research community. For each instrument, ARM calculates the ratio of the actual number of processed data records received daily at the ARM Data Archive to the expected number of data records. DOE requires national user facilities to report time-based operating data.

  11. A characterization and evaluation of coal liquefaction process streams. Quarterly technical progress report, July 1--September 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Robbins, G.A.; Brandes, S.D.; Winschel, R.A.; Burke, F.P.

    1995-12-01

    The objectives of this project are to support the DOE direct coal liquefaction process development program and to improve the useful application of analytical chemistry to direct coal liquefaction process development. Independent analyses by well-established methods will be obtained of samples produced in direct coal liquefaction processes under evaluation by DOE. Additionally, analytical instruments and techniques which are currently underutilized for the purpose of examining coal-derived samples will be evaluated. The data obtained from this study will be used to help guide current process development and to develop an improved data base on coal and coal liquids properties. A sample bank will be established and maintained for use in this project and will be available for use by other researchers. The reactivity of the non-distillable resids toward hydrocracking at liquefaction conditions (i.e., resid reactivity) will be examined. From the literature and data experimentally obtained, a mathematical kinetic model of resid conversion will be constructed. It is anticipated that such a model will provide insights useful for improving process performance and thus the economics of direct coal liquefaction. Some of the contract activities for this quarter are: We completed many of the analyses on the 81 samples received from HTI bench-scale run CMSL-9, in which coal, coal/mixed plastics, and coal/high density polyethylene were fed; Liquid chromatographic separations of the 15 samples in the University of Delaware sample set were completed; and WRI completed CP/MAS {sup 13}C-NMR analyses on the Delaware sample set.

  12. A review of IAEA's technical co-operation programme

    International Nuclear Information System (INIS)

    Samiei, M.

    2004-01-01

    Full text: The Technical Co-operation (TC) Programme is part of the Agency's mandate 'to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world.' The IAEA's role under this Programme is that of a scientific and technical agency making a discrete but significant contribution to sustainable development goals through the transfer of nuclear science and technology. TC is a high impact programme focusing on development needs with about 800 active projects annually with a budget of over $70M, 30% of which is targeted on training and capacity building in over 100 Member States. Since 1970, over 80,000 scientists and specialists from developing countries have been trained in nuclear science and technology and in nuclear power and safety. A number of trends in the world at large will be likely to influence the Agency's TC programme in the next several years: The use of nuclear technologies in developing countries is growing as local infrastructures improve and technology transfer increases, especially among developing countries; Some countries and institutions are becoming more self-reliant as viable markets develop for nuclear technology, based on an increased awareness of their benefits; As facilities age, safe strategies for life extension and for decommissioning are assuming increasing importance, while there is some renewed positive attention to nuclear power in several parts of the world. Concern is increasing related to the potential for malicious acts involving nuclear facilities or unsecured nuclear and other radioactive material. As the nuclear workforce ages, the management of nuclear knowledge is gaining increasing importance, including the need to maintain the safety and security of nuclear installations and their continued reliable operation. It is difficult to forecast precisely how these trends will influence the assistance requested by Member States, but it is already clear that there will be increased

  13. Projects at the Western Environmental Technology Office. Quarterly technical progress report, July 1, 1995--September 30, 1995

    International Nuclear Information System (INIS)

    1996-01-01

    The goal of this project is to demonstrate the technical and economic feasibility of commercializing a biotechnology that uses plants to remediate soils, sediments, surface waters, and groundwaters contaminated by heavy metals and radionuclides. This technology, known as phytoremediation, is particularly suited to remediation of soils or water where low levels of contaminants are widespread. Project objectives are to provide an accurate estimate of the capability and rate of phytoremediation for removal of contaminants of concern from soils and groundwaters at Department of Energy (DOE) sites and to develop data suitable for engineering design and economic feasibility evaluations, including methods for destruction or final disposition of plants containing contaminants of concern. The bioremediation systems being evaluated could be less expensive than soil removal and treatment systems, given the areal extent and topography of sites under consideration and the investment of energy and money in soil-moving and -treating processes. In situ technology may receive regulatory acceptance more easily than ex situ treatments requiring excavation, processing, and replacement of surface soils. In addition, phytoremediation may be viable for cleanup of contaminated waters, either as the primary treatment or the final polishing stage, depending on the contaminant concentrations and process economics considerations

  14. Projects at the Western Environmental Technology Office. Quarterly technical progress report, July 1, 1995--September 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    The goal of this project is to demonstrate the technical and economic feasibility of commercializing a biotechnology that uses plants to remediate soils, sediments, surface waters, and groundwaters contaminated by heavy metals and radionuclides. This technology, known as phytoremediation, is particularly suited to remediation of soils or water where low levels of contaminants are widespread. Project objectives are to provide an accurate estimate of the capability and rate of phytoremediation for removal of contaminants of concern from soils and groundwaters at Department of Energy (DOE) sites and to develop data suitable for engineering design and economic feasibility evaluations, including methods for destruction or final disposition of plants containing contaminants of concern. The bioremediation systems being evaluated could be less expensive than soil removal and treatment systems, given the areal extent and topography of sites under consideration and the investment of energy and money in soil-moving and -treating processes. In situ technology may receive regulatory acceptance more easily than ex situ treatments requiring excavation, processing, and replacement of surface soils. In addition, phytoremediation may be viable for cleanup of contaminated waters, either as the primary treatment or the final polishing stage, depending on the contaminant concentrations and process economics considerations.

  15. The Agency's technical co-operation activities in 1993

    International Nuclear Information System (INIS)

    1994-08-01

    This document reviews the IAEA's Technical Cooperation activities for 1993. Apart from an overview, the report contains reviews by Agency programmes and technical divisions, by area, by component and by fund. Summaries of project implementation are also included, as well as indications of the achievements of projects completed in 1993

  16. BX in situ oil shale project. Annual technical progress report, March 1, 1979-February 29, 1980 and quarterly technical progress report, December 1, 1979-February 29, 1980

    Energy Technology Data Exchange (ETDEWEB)

    Dougan, P.M.

    1980-03-20

    During the year, design, construction and installation of all project equipment was completed, and continuous steam injection began on September 18, 1979 and continued until February 29, 1980. In the five-month period of steam injection, 235,060 barrels of water as steam at an average wellhead pressure of 1199 psig and an average wellhead temperature of 456/sup 0/F were injected into the eight project injection wells. Operation of the project at design temperature and pressure (1000/sup 0/F and 1500 psig) was not possible due to continuing problems with surface equipment. Environmental monitoring at the project site continued during startup and operation.

  17. TECHNICAL BASIS FOR VENTILATION REQUIREMENTS IN TANK FARMS OPERATING SPECIFICATIONS DOCUMENTS

    Energy Technology Data Exchange (ETDEWEB)

    BERGLIN, E J

    2003-06-23

    This report provides the technical basis for high efficiency particulate air filter (HEPA) for Hanford tank farm ventilation systems (sometimes known as heating, ventilation and air conditioning [HVAC]) to support limits defined in Process Engineering Operating Specification Documents (OSDs). This technical basis included a review of older technical basis and provides clarifications, as necessary, to technical basis limit revisions or justification. This document provides an updated technical basis for tank farm ventilation systems related to Operation Specification Documents (OSDs) for double-shell tanks (DSTs), single-shell tanks (SSTs), double-contained receiver tanks (DCRTs), catch tanks, and various other miscellaneous facilities.

  18. Kansas State University: DOE/KEURP Site Operator Program. Year 4, fourth quarterly report, April 1, 1995--June 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    Kansas State University, in support of a DOE and Kansas Electric Utilities Research Program subject contract, continues to test, evaluate, demonstrate, and develop electric vehicle and infrastructure technology. K-State is operating two Soleq EVcort vehicles. During this reporting period both vehicles were brought back to full operational status after warranty service was completed by Soleq. Vehicle failures occurred due to three unrelated battery cable failures in addition to the replacement of one battery. Both vehicles are being operated on a routine basis. K-State, along with York Technical College, has established a relationship with Troy Design and Manufacturing (TDM) Redford, Michigan. K-State has ordered no less than four Ford Ranger electric trucks from TDM. K-State is involved in the steering committee that is monitoring and refining information to direct the design and testing of these new technology vehicles. TDM should become the first automotive manufacturer certified by one of the Big Three under their Quality Vehicle Manufacturer program. Kansas State University and the Kansas Electric Utility Research Program look forward to working with TDM on their new EV program.

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

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-31

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

  20. 78 FR 5167 - BE-9: Quarterly Survey of Foreign Airline Operators' Revenues and Expenses in the United States

    Science.gov (United States)

    2013-01-24

    ... 45 days after the end of each calendar quarter. The BE-9 survey forms and instructions are available... institution, or other entity or instrumentality thereof, including a government-sponsored agency). (b) United... www.bea.gov/efile . Additionally, copies of the survey forms and instructions, which contain complete...

  1. Computational modeling and experimental studies on NO{sub x} reduction under pulverized coal combustion conditions. Third quarterly technical progress report, July 1, 1995--September 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Kumpaty, S.K.; Subramanian, K.

    1995-12-31

    An experimental plan outlining the first year`s activity was sent to Dr. Lori Gould, Project Officer/Contracting Officer`s Technical Representative on April 24, 1995. An approval was received with some questions on June 15, 1995. However, with some foresight of the director of the in-house combustion group of the PETC, Dr. Ekmann, a tentative hold-off on the purchase of the equipment was requested by the project officer on June 29, 1995. Enclosed with that request were some of Dr. Ekmann`s concerns. The research team spent the month of July in study of pertinent literature as well as in the preparation of the responses to Dr. Gould`s comments and Dr. Ekmann`s concerns. These responses included the choice of the reactor, reactor design, rate of gas heating, detailed test matrix and answers to host of other comments. Upon review of the above information submitted on July 24, 1995 by the Rust research team, the project officer called for a conference call on September 6, 1995 which involved the PI (Dr. Kumpaty), the research consultant (Mr. Subramanian), Dr. Gould and Dr. Ekmann. Dr. Ekmann insisted that further calculations be made on the rate of gas heating without taking radiation into account. Accordingly, calculations pertaining to the rate of gas heating based on convection were performed and submitted to Dr. Ekmann on September 13, 1995. This report contains the information emerged through the dialogue between the Rust College research team and the PETC represented by Dr. Gould and Dr. Ekmann during this quarter.

  2. IAEA technical co-operation with least developed Member States. Special evaluation

    International Nuclear Information System (INIS)

    1993-01-01

    The main purposes of this evaluation were to: Review the overall situation with regard to IAEA technical co-operation with least developed Member States, including specific conditions in nuclear-related activities prevailing in these countries, approaches and practices used by the IAEA in providing assistance to LDCs, and the main results of the co-operation in question. Identify any adjustments to technical co-operation with LDC Member States that may strengthen this activity

  3. Emergency Management Operations Process Mapping: Public Safety Technical Program Study

    Science.gov (United States)

    2011-02-01

    services Operational Activity Collect and Manage Cash Donations Once activated, refer cash donations to appropriate voluntary organizations...recovery operations. Operational Activity Conduct Euthanasia /Disposal Provide humane methods to euthanize affected animals to stop the spread of the...issue stop movement orders, and initiate animal vaccination and treatment programs, euthanasia efforts, or other protective measures designed to control

  4. Technical co-operation report for 2000. Report by the Director General

    International Nuclear Information System (INIS)

    2001-01-01

    This report covers three separate topics. Part one fulfills the Agency's obligation under the General Conference resolution GC(44)/RES/18 to report on the Strengthening of Technical Co-operation. It covers the period from 1 April 2000 to 31 March 2001. The report examines the finalization of the 2001-2002 technical co-operation programme and several key concepts of the Technical Co-operation Strategy such as Partners in Development, Technical Co-operation among Developing Countries, and the continuing evolution of Regional Resource Centres. Reflecting an important trend in the technical co-operation programme, which was mandated by the General Conference, the report describes the results achieved in several programmes in least developed countries. Part two reports on the major achievements of the technical co-operation programme in 2000 in the different regions of the world. Part three presents a summary of the financial and non-financial parameters of the technical co-operation programme. The supplement to the report provides a more detailed review of resources and contributions, disbursements and non-financial indicators

  5. Technical co-operation report for 2000. Report by the Director General

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This report covers three separate topics. Part one fulfills the Agency's obligation under the General Conference resolution GC(44)/RES/18 to report on the Strengthening of Technical Co-operation. It covers the period from 1 April 2000 to 31 March 2001. The report examines the finalization of the 2001-2002 technical co-operation programme and several key concepts of the Technical Co-operation Strategy such as Partners in Development, Technical Co-operation among Developing Countries, and the continuing evolution of Regional Resource Centres. Reflecting an important trend in the technical co-operation programme, which was mandated by the General Conference, the report describes the results achieved in several programmes in least developed countries. Part two reports on the major achievements of the technical co-operation programme in 2000 in the different regions of the world. Part three presents a summary of the financial and non-financial parameters of the technical co-operation programme. The supplement to the report provides a more detailed review of resources and contributions, disbursements and non-financial indicators.

  6. Environmental guidance documents for exploration, development, Production, and transportation of crude oil and natural gas in texas: Quarterly technical report, January 1, 1997-March 31, 1997

    International Nuclear Information System (INIS)

    Savage, L.

    1997-01-01

    The following technical report provides a detailed status report of the DOE grant project entitled ''Environmental Guidance Documents for Exploration, Development, Production, and Transportation of Crude Oil and Natural Gas in Texas.'' The grant funding allocated is for the purpose of provided the Railroad Commission of Texas (Commission) with resources and capabilities to draft, publish and distribute documents that provide guidance to oil and gas operators on issues concerning oil and gas naturally occurring radioactive material (NORM) waste, oil and gas hazardous waste, remediation of crude oil spills, management of non-hazardous oil and gas wastes, and mechanical integrity testing of Class II injection and disposal wells

  7. Operation and maintenance of the technical installations in buildings

    DEFF Research Database (Denmark)

    Nielsen, O.(red.)

    The report contains twelve papers from a seminar on operation and maintenance, held at the Danish Building Research Institute in October 1976. The papers deal, among other things, with dimensioning and balancing of pipesystems, design of ventilating systems for adequate operation and maintenance,......, cost and quality in maintenance, maintenance service companies, as well as organization and training for building services maintenance....

  8. [Current value, technic and indications for obstetrical operations].

    Science.gov (United States)

    Bayer, H

    1983-01-01

    Starting point of this survey is the 1954 paper about obstetrical operations from H. Kraatz. It is demonstrated, that there were and there are defined principles, which continue to exist unchanged. They are the fundamentals of indication and technique of operations in obstetrics. Nevertheless there are distinct changes, too, caused by two factors, progress in medicine (development of antibiotics, anaesthesiology and neonatology) as well as change of aspect in obstetrics (e.g. toxemias of pregnancy, preterm labour). The methods are discussed in detail. Operations by vaginal route come in the foreground in the last years more again. They should be preferred in maternal interest. The enlarged indication for caesarean section was not able to succeed on a large scale. An uniform procedure is proposed both in cephalic and breech presentation, and the new formulated preconditions to these operations are discussed. All three techniques two abdominal ones and one vaginal one) are demanded in caesarean sections, because they come into question in special situations. There is a change in operative indications in cases of bleeding, because of an early diagnosis by ultrasound. The qualification and experience of the obstetrician is more decisive than the selected method of operation or the instrument's type. Therefore there should not be any cut in instruction and training. The versatility of operative technique is a prerequisite to a qualified indication.

  9. Environmental management system for transportation maintenance operations : [technical brief].

    Science.gov (United States)

    2014-04-01

    This report provides the framework for the environmental management system to analyze : greenhouse gas emissions from transportation maintenance operations. The system enables user : to compare different scenarios and make informed decisions to minim...

  10. Annual meeting on nuclear technology 1980. Technical meeting: Operating experiences

    International Nuclear Information System (INIS)

    1980-01-01

    In addition to general experiences, experiences in reactor operation with relation to the Phenix reactor, KNK-2 reactor, the AVR reactor, the BWR-type KKI-reactor, the Philippsburg-1 reactor and the Obrigheim reactor are described. (DG) [de

  11. Coaching Non-technical Skills Improves Surgical Residents' Performance in a Simulated Operating Room.

    Science.gov (United States)

    Yule, Steven; Parker, Sarah Henrickson; Wilkinson, Jill; McKinley, Aileen; MacDonald, Jamie; Neill, Adrian; McAdam, Tim

    2015-01-01

    To investigate the effect of coaching on non-technical skills and performance during laparoscopic cholecystectomy in a simulated operating room (OR). Non-technical skills (situation awareness, decision making, teamwork, and leadership) underpin technical ability and are critical to the success of operations and the safety of patients in the OR. The rate of developing assessment tools in this area has outpaced development of workable interventions to improve non-technical skills in surgical training and beyond. A randomized trial was conducted with senior surgical residents (n = 16). Participants were randomized to receive either non-technical skills coaching (intervention) or to self-reflect (control) after each of 5 simulated operations. Coaching was based on the Non-Technical Skills For Surgeons (NOTSS) behavior observation system. Surgeon-coaches trained in this method coached participants in the intervention group for 10 minutes after each simulation. Primary outcome measure was non-technical skills, assessed from video by a surgeon using the NOTSS system. Secondary outcomes were time to call for help during bleeding, operative time, and path length of laparoscopic instruments. Non-technical skills improved in the intervention group from scenario 1 to scenario 5 compared with those in the control group (p = 0.04). The intervention group was faster to call for help when faced with unstoppable bleeding in the final scenario (no. 5; p = 0.03). Coaching improved residents' non-technical skills in the simulated OR compared with those in the control group. Important next steps are to implement non-technical skills coaching in the real OR and assess effect on clinically important process measures and patient outcomes. Copyright © 2015 Association of Program Directors in Surgery. Published by Elsevier Inc. All rights reserved.

  12. 10 CFR 34.29 - Quarterly inventory.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Quarterly inventory. 34.29 Section 34.29 Energy NUCLEAR... RADIOGRAPHIC OPERATIONS Equipment § 34.29 Quarterly inventory. (a) Each licensee shall conduct a quarterly physical inventory to account for all sealed sources and for devices containing depleted uranium received...

  13. TMI-related requirements for new operating licenses. Technical report

    International Nuclear Information System (INIS)

    1980-06-01

    There are four types of TMI-related requirements and actions approved by the Commission for new operating licenses: (1) those required to be completed by a license applicant prior to receiving a fuel-loading and low-power testing license, (2) those required to be completed by a license applicant prior to receiving a license to operate at appreciable power levels up to full power, (3) those the NRC will take prior to issuing a fuel-loading and low-power testing or a full-power operating license, and (4) those required to be completed by a licensee prior to a specified date. In this report, only those dated requirements that have already been issued are of interest. Other dated requirements are expected to be issued in the future as work progresses in accordance with the TMI Action Plan. This report summarizes the several parts of the list of TMI-related requirements approved by the Commission for new operating licenses

  14. Nuclear power operating experience and technical improvement in Japan

    International Nuclear Information System (INIS)

    Toyota, M.

    1983-01-01

    LWR technology in Japan, originally introduced from the United States of America, is now almost entirely supplied domestically. During the initial stage of plant operation, electric power companies experienced various troubles such as intergranular stress corrosion cracking (IGSCC) in the piping in BWRs and steam generator (S/G) tube leaks in PWRs, which once reduced the capacity factor to about 40%. As a result of efforts to investigate the causes of the troubles and to establish countermeasures, which were applied to the plants in operation and under construction for improvement, as well as to shorten the period of regular inspection and to extend the operation cycle, the capacity factor has been improved to 60% since 1980. In 1975 an LWR improvement and standardization programme was launched to aim at improvement of reliability and availability factor and reduction of occupational radiation exposure with the development of domestic technology based on construction and operating experience. The First Phase Programme, which ran from 1975 to 1977, established countermeasures to preclude these troubles and improved workability by enlargement of the containment vessel. The Second Phase Programme followed and ran until 1981. The major steps taken during this period include the adoption of new IGSCC-resistant material and improved core design for BWRs and the improvement of fuels and S/Gs for PWRs. With these improvements, the capacity factor is now expected to reach a 75% level and occupational radiation exposure should be reduced by 50%. A Third Phase Programme will centre on the test and development programme for advanced BWRs and PWRs now under way to further improve the availability factor and reliability while also minimizing radiation exposure. (author)

  15. Human Performance in Continuous Operations. Volume 3. Technical Documentation

    Science.gov (United States)

    1980-03-01

    completed for the U. S. Commander, V Corps. Artillery, by Manning (1978). Manning collected information which bears on the following three questions: 0 Can...performance data were not collected in these pre- liminary studies. Field Studies of Continuous Tank OperationsLI __ _ _ __ _ _ _ To simulate a combat...on routine, monotonous tasks tends A show rapid and severe decrement after peri- odk of more than 24 hours without sleep. I Increasing task complexity

  16. Bi-gas pilot plant operation. Technical progress report, 1 July 1980-30 September 1980

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-01-01

    The stainless steel process gas line from the gasifier to the gas washer was replaced with chrome molybdenum steel. Test G-13 was the longest to date and was characterized by smooth start-up and operation, long Stage I thermocouple life, and collection of much material balance data. Stress corrosion cracking in several areas of the process gas line delayed start-up of Test G-14 and a large part of the quarter was spent in replacing this piping. The results of test G-13 are described in detail. Conclusions for the test and recommendation are given, especially for burner modifications, prevention of calcium carbonate deposits, etc.

  17. Special Operations Forces (SOF) technical analysis and evaluation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1987-08-31

    In response to Task Order 001, Los Alamos National Laboratory Contract 9-L5H-1508P-1, Betac Corporation is pleased to provide ten quick-response, short-term analytical papers in support of Low Intensity Conflict (LIC) and Special Operations (SO). The papers are study methodologies which provide background, baseline, concepts, approaches, and recommendations in the mission areas identified in the Statement of Work. Although the Statement of Work specifies only nine papers, a tenth paper has been included addressing Command Relationships, since this subject affects all other topics and is of critical importance to USCINCSOC in establishing the United States Special Operations Command (USSOCOM). Each paper addresses the feasibility of further effort in each area of interest. The ten papers address: (1) mission support systems; (2) research, development, and acquisition; (3) headquarters equipment; (4) C3I architecture; (5) intelligence dissemination; (6) intelligence collection management; (7) intelligence support to SOF targeting; (8) joint mission area analysis (JMAA); (9) joint SOF master plan; and (10) command relationships.

  18. 43 CFR 23.5 - Technical examination of prospective surface exploration and mining operations.

    Science.gov (United States)

    2010-10-01

    ... mining operations vary widely with respect to topography, climate, surrounding land uses, proximity to... surface exploration and mining operations. 23.5 Section 23.5 Public Lands: Interior Office of the Secretary of the Interior SURFACE EXPLORATION, MINING AND RECLAMATION OF LANDS § 23.5 Technical examination...

  19. A technical system to improve the operational monitoring of the Zaporozh'ye nuclear power plant

    International Nuclear Information System (INIS)

    Beyer, M.; Carl, H.; Schumann, P.; Seidel, A.; Weiss, F.-P.; Zschau, J.; Nowak, K.

    1997-01-01

    As part of a programme of cooperation with Central and Eastern European states, a technical system has been established for the Zaporozhe nuclear power plant, which complements existing operational checking and monitoring facilities with modern means of information technology. It makes it possible to continuously monitor the state of the units in normal operation and in cases of anomalies or incidents. The parameters selected for monitoring are listed, and the system of automatic evaluation at the power plant site is described in detail. Test operation of the technical system started in late 1995 and the industrial testing phase in mid-1996. (A.K.)

  20. Development and testing of industrial scale, coal fired combustion system, Phase 3. Eighteenth quarterly technical progress report, April 1, 1996--June 30, 1996

    Energy Technology Data Exchange (ETDEWEB)

    Zauderer, B.

    1996-08-18

    In the second quarter of calendar year 1996, 16 days of combust- boiler tests were performed, including 2 days of tests on a parallel DOE sponsored project on sulfur retention in a slagging combustor. Between tests, modifications and improvements that were indicated by these tests were implemented. This brings the total number of test days to the end of June in the task 5 effort to 28, increased to 36 as of the date of this Report, 8/18/96. This compares with a total of 63 test days needed to complete the task 5 test effort. It is important to note that the only major modification to the Williamsport combustor has been the addition of a new downstream section, which lengthens the combustor and improves the combustor-boiler interface. The original combustor section, which includes the fuel, air, and cooling water delivery systems remained basically unchanged. Only the refractory liner was completely replaced, a task which occurs on an annual basis in all commercial slagging utility combustors. Therefore, this combustor has been operated since 1988 without replacement. The tests in the present reporting period are of major significance in that beginning with the first test on March 31st, for the first time slagging opening conditions were achieved in the upgraded combustor. The first results showed that the present 20 MMBtu/hr combustor design is far superior to the previous one tested since 1988 in Williamsport, PA. The most important change is that over 95% of the slag was drained from the slag tap in the combustor. This compares with an range of one-third to one-half in Williamsport. In the latter, the balance of the slag flowed out of the exit nozzle into the boiler floor. In addition, the overall system performance, including the combustor, boiler, and stack equipment, ranged from good to excellent. Those areas requiring improvement were of a nature that could be corrected with some work. but in no case were the problems encountered of a barrier type.

  1. Technical refolding of proteins: Do we have freedom to operate?

    Science.gov (United States)

    Eiberle, Maria K; Jungbauer, Alois

    2010-06-01

    Expression as inclusion bodies in Escherichia coli is a widely used method for the large-scale production of therapeutic proteins that do not require post-translational modifications. High expression yields and simple recovery steps of inclusion bodies from the host cells are attractive features industrially. However, the value of an inclusion body-based process is dominated by the solubilization and refolding technologies. Scale-invariant technologies that are economical and applicable for a wide range of proteins are requested by industry. The main challenge is to convert the denatured protein into its native conformation at high yields. Refolding competes with misfolding and aggregation. Thus, the yield of native monomer depends strongly on the initial protein concentrations in the refolding solution. Reasonable yields are attained at low concentrations (freedom to operate.

  2. Manpower development for safe operation of nuclear power plant. China. Seminar on the technical support functions. Activity: 6.1.1-Task-03. Technical report

    International Nuclear Information System (INIS)

    Bouget, Y.H.

    1994-01-01

    The seminar discussed the objectives, organization and scope of work of the Central and Site Technical Service Department in support of operating NPP; transfer of capability to establish and maintain an efficient operation support; defined the responsibilities and interface between on site and Central Technical Staff

  3. Control rod guide tube wear in operating reactors; operating experience report. Technical report December 1977-December 1979

    International Nuclear Information System (INIS)

    Riggs, R.

    1980-04-01

    Evidence of control rod guide tube wear has been observed in operating pressurized water reactors. The cause of this wear is identified as flow-induced vibration of the control rods. This report describes the measures being taken by both the industry and the NRC to deal with this matter. The staff also presents its technical positions and requirements to support continued operation of the plants as of December 1979 pending completion of this generic effort

  4. Technical evolution and operation of French CO2 cooled reactors (UNGG)

    International Nuclear Information System (INIS)

    Berthion, Y.

    1986-10-01

    The technical evolution of the five French CO 2 cooled reactors (UNGG) from 1981 to 1986 needs to be outlined. These technical evolutions concerned the fuel element of Bugey 1 which is now slightly enriched, as well as the load reduction operation required by the grid. In addition work in underway to increase the safety at the two St Laurent units, or to repair the hot steel upper-structures of Chinon-3 unit

  5. Technical challenges to energy systems' operation and markets

    Energy Technology Data Exchange (ETDEWEB)

    Soerensen, P.; Meibom, P.; Gehrke, O. [Risoe National Lab. (Denmark); Oestergaard, J. [Technical Univ. of Denmark (Denmark)

    2006-11-15

    A future energy system that includes a high proportion of renewable energy will be expected to meet the same requirements for security of supply and economic efficiency as the energy systems of today, while delivering better environmental performance, especially with regard to CO{sub 2} emissions. Security of supply refers to the long-term reliability of fuel supply; especially in power systems, it also covers short-term requirements for system stability and adequacy. Economic efficiency is concerned with getting the best from the significant amounts of money, human capital and natural resources involved in an energy system. Integral to economic efficiency in energy systems is the presence of well-functioning markets for energy services. The variability and reduced predictability of a number of renewable energy sources, notably wind power, create specific challenges for future energy systems compared to those of today. Power transmission will also become an issue, as the areas with good potential for wind power and wave energy are often located some distance from the centres of power consumption. This chapter describes the challenges involved, and possible solutions to these, with a focus on power systems. The chapter is divided into two sections reflecting the fact that some challenges relate to managing the power system in its normal operation mode, whereas others are specific to fault conditions. (au)

  6. Non-technical skills of surgeons and anaesthetists in simulated operating theatre crises.

    Science.gov (United States)

    Doumouras, A G; Hamidi, M; Lung, K; Tarola, C L; Tsao, M W; Scott, J W; Smink, D S; Yule, S

    2017-07-01

    Deficiencies in non-technical skills (NTS) have been increasingly implicated in avoidable operating theatre errors. Accordingly, this study sought to characterize the impact of surgeon and anaesthetist non-technical skills on time to crisis resolution in a simulated operating theatre. Non-technical skills were assessed during 26 simulated crises (haemorrhage and airway emergency) performed by surgical teams. Teams consisted of surgeons, anaesthetists and nurses. Behaviour was assessed by four trained raters using the Non-Technical Skills for Surgeons (NOTSS) and Anaesthetists' Non-Technical Skills (ANTS) rating scales before and during the crisis phase of each scenario. The primary endpoint was time to crisis resolution; secondary endpoints included NTS scores before and during the crisis. A cross-classified linear mixed-effects model was used for the final analysis. Thirteen different surgical teams were assessed. Higher NTS ratings resulted in significantly faster crisis resolution. For anaesthetists, every 1-point increase in ANTS score was associated with a decrease of 53·50 (95 per cent c.i. 31·13 to 75·87) s in time to crisis resolution (P technical skills scores were lower during the crisis phase of the scenarios than those measured before the crisis for both surgeons and anaesthetists. A higher level of NTS of surgeons and anaesthetists led to quicker crisis resolution in a simulated operating theatre environment. © 2017 BJS Society Ltd Published by John Wiley & Sons Ltd.

  7. Assessing Nurse Anaesthetists' Non-Technical Skills in the operating room.

    Science.gov (United States)

    Lyk-Jensen, H T; Jepsen, R M H G; Spanager, L; Dieckmann, P; Østergaard, D

    2014-08-01

    Incident reporting and fieldwork in operating rooms have shown that some of the errors that arise in anaesthesia relate to inadequate use of non-technical skills. To provide a tool for training and feedback on nurse anaesthetists' non-technical skills, this study aimed to adapt the Anaesthetists' Non-Technical Skills (ANTS) as a behavioural marker system for the formative assessment of nurse anaesthetists' non-technical skills in the operating room. A qualitative approach with focus group interviews was used to identify the non-technical skills of nurse anaesthetists in the operating room. The interview data were transcribed verbatim. Directed content analysis was used to code and sort data deductively into the ANTS categories: task management, team working, situation awareness and decision making. The prototype named Nurse Anaesthetists' Non-Technical Skills (N-ANTS) was presented and discussed in a group of subject matter experts to ensure face validity. The N-ANTS system consists of the same four categories as ANTS and 15 underlying elements. Three to five good and poor behavioural markers for each element were identified. The headings and definitions of the categories and elements were adjusted to encompass the behavioural markers in N-ANTS. The differences that emerged mainly reflected statements regarding the establishment of role, competence, and task delegation. A behavioural marker system, N-ANTS, for nurse anaesthetists was adapted from a behavioural marker system, ANTS, for anaesthesiologists. © 2014 The Acta Anaesthesiologica Scandinavica Foundation. Published by John Wiley & Sons Ltd.

  8. Additive Manufacturing (AM) in Expeditionary Operations: Current Needs, Technical Challenges, and Opportunities

    Science.gov (United States)

    2016-06-01

    REPORT TYPE AND DATES COVERED Master’s Thesis 06-30-2014 to 06-17-2016 4. TITLE AND SUBTITLE ADDITIVE MANUFACTURING (AM) IN EXPEDITIONARY OPERATIONS: CUR...CODE 13. ABSTRACT (maximum 200 words) Additive manufacturing (AM), or 3D printing, is poised to change the world of military expeditionary operations...unlimited ADDITIVE MANUFACTURING (AM) IN EXPEDITIONARY OPERATIONS: CURRENT NEEDS, TECHNICAL CHALLENGES, AND OPPORTUNITIES Matthew Daniel Friedell Captain

  9. Operating environment threats influence on the maritime ferry technical system safety – the numerical approach

    Directory of Open Access Journals (Sweden)

    Kuligowska Ewa

    2017-06-01

    Full Text Available The material given in this paper delivers the procedure for numerical approach that allows finding the main practically important safety characteristics of the complex technical systems at the variable operation conditions including operating environment threats. The obtained results are applied to the safety evaluation of the maritime ferry technical system. It is assumed that the conditional safety functions are different at various operation states and have the exponential forms. Using the procedure and the program written in Mathematica, the considered maritime ferry technical system main characteristics including: the conditional and the unconditional expected values and standard deviations of the system lifetimes, the unconditional safety function and the risk function are determined.

  10. Post waterflood CO2 miscible flood in light oil fluvial - dominated deltaic reservoirs. Technical progress report, October 1, 1994--December 30, 1994. 1st Quarter, fiscal year 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-01-15

    Production is averaging about 450 BOPD for the quarter. The fluctuation was primarily due to a temporary shutdown of CO{sub 2} delivery and maturing of the first WAG cycle. CO{sub 2} and water injection were reversed again in order to optimize changing yields and water cuts in the producing wells. Measured BHP was close to the anticipated value. A limited CO{sub 2} volume of 120 MMCF was injected to stimulate well Kuhn No. 6 to test the Huff-Puff process, since the well did not respond to CO{sub 2} injection from the main reservoir. The well will be placed on February 1, 1995. Total CO{sub 2} injection averaged this quarter about 8.8 MMCFD, including 3.6 MMCFD purchased CO{sub 2} from Cardox. The stratigraphy of the sand deposits is also discussed.

  11. Manpower development for safe operation of nuclear power plant. China. Seminar on the technical support functions. Activity: 6.1.1-Task-03. Technical report

    International Nuclear Information System (INIS)

    Groom, S.H.

    1994-01-01

    The workshop which was intended to present operating experiences from utilities with a wide range of numbers of operating nuclear units. The speaker, S.H. Groom, presented N.B. Power's experience with a single nuclear unit, and intended to: Present the objectives, organization, and scope of work of the central and site Technical Service groups within N.B. Power which support the operation of the Point Lepreau NGS; Define responsibilities of, and interfaces between the on-site and the central technical service staff; Recommend methods for the establishment and maintenance of an efficient technical support group for the operation of any nuclear power plant

  12. 7. IAEA Technical Meeting on Steady State Operation of Magnetic Fusion Devices - Booklet of abstracts

    International Nuclear Information System (INIS)

    2015-01-01

    This meeting has provided an appropriate forum to discuss current issues covering a wide range of technical topics related to the steady state operation issues and also to encourage forecast of the ITER performances. The technical meeting includes invited and contributed papers. The topics that have been dealt with are: 1) Superconducting devices (ITER, KSTAR, Tore-Supra, HT-7U, EAST, LHD, Wendelstein-7-X,...); 2) Long-pulse operation and advanced tokamak physics; 3) steady state fusion technologies; 4) Long pulse heating and current drive; 5) Particle control and power exhaust, and 6) ITER-related research and development issues. This document gathers the abstracts

  13. Technical requirements on knowledge base and instrumentation system for decision making in plant operation and maintenance

    International Nuclear Information System (INIS)

    Kitamura, Masaharu; Yoshikawa, Shinji; Hasegawa, Makoto

    1998-03-01

    A series of technical surveys and studies are described in this report to examine and identify technical requirements to be posed on knowledge base and instrumentation system as the fundamental in high reliability computational decision making in operation and maintenance of nuclear power plants. Monitoring and diagnosis are focused as the important tasks among the operation/maintenance-related tasks. A concrete monitoring and diagnosis system configuration has been proposed consisting of distributed symptom database and of on-demand measurement subsystem. An prototype of the proposed system configuration has been successfully verified. (author)

  14. Technical co-operation report for 2002. Report by the Director General

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-08-01

    General Conference resolution GC(46)/RES/10 reiterated the need to strengthen the technical co- operation programme and requested the Director General to report to the Board of Governors periodically and to the General Conference at its forty-seventh (2003) session on the implementation of resolution GC(46)/RES/10. Part A of this report responds to the General Conference resolution by providing an overview of the progress achieved in technical co-operation policies, strategies, working relations, and internal management during the period 1 April 2002 to 31 March 2003, as well as the major new challenges facing the technical co-operation programme. Part B reports on operational activities and programme performance at the country and regional levels during the calendar year 2002, and Part C reviews the use of financial and human resources in the programme at an aggregate level. As part of its efforts to refine policies for improving programme development, the Agency reviewed the Technical Co-operation Strategy in 2002. The resulting document, The Technical Co-operation Strategy: the 2002 Review (document GOV/INF/2002/8/Mod.1), states that the strategic goal originally identified in the Strategy in 1997 remains valid, and defines four objectives to guide the technical co-operation programme: applying the central criterion (strong government commitment), developing strategic partnerships, increasing the level of funding for technical co-operation, and promoting greater sustainability and self-reliance of nuclear institutions. In line with the Technical Co-operation Strategy, one of the key features of the Agency.s work in 2002 was continuing consultations with Member States at both the policy and operational levels on the management of the ongoing technical co-operation programme and on planning for future activities. The dialogue with Member States aimed at clarifying the strategic objectives and key tools for the utilization of resources to achieve maximum

  15. Non-technical skills of the operating theatre scrub nurse: literature review.

    Science.gov (United States)

    Mitchell, Lucy; Flin, Rhona

    2008-07-01

    This paper is a report of a review to identify the non-technical (cognitive and social) skills used by scrub nurses. Recognition that failures in non-technical skills contributed to accidents in high-risk industries led to the development of research programmes to study the role of cognition and social interactions in operational safety. Recently, psychological research in operating theatres has revealed the importance of non-technical skills in safe and efficient performance. Most of the studies to date have focused on anaesthetists and surgeons. On-line sources and university library catalogues, publications of the Association for Perioperative Practice, National Association of Theatre Nurses and Association of Peri-Operative Registered Nurses were searched in 2007. Studies were included in the review if they presented data from scrub nurses on one or more of their non-technical skills. These findings were examined in relation to an existing medical non-technical skills framework with categories of communication, teamwork, leadership, situation awareness and decision-making. Of 424 publications retrieved, 13 were reviewed in detail. Ten concerned communication and eight of those also had data on teamwork. In 11 papers teamwork was examined, and one focused on nurses' situation awareness, teamwork and communication. None of the papers we reviewed examined leadership or decision-making by scrub nurses. Further work is needed to identify formally the non-technical skills which are important to the role of scrub nurse and then to design training in the identified non-technical skills during the education and development of scrub nurses.

  16. The Agency's Technical Co-operation activities in 1984. Report by the Director General

    International Nuclear Information System (INIS)

    1985-08-01

    The year 1984 can be described as one during which efforts were made to increase momentum in the development co-operation between the Agency and its Member States while continuing to improve the quality of the technical assistance rendered. For the first time, the adjusted programme exceeded $50 million. During the year, changes were introduced in the administration of the programme in line with recommendations endorsed by the Board in 1983 at the end of its first technical co-operation policy review. In 1984, when the new technical co-operation policies were applied, there were three principal aims. First, the flow of Technical Assistance and Co-operation Fund resources was to be improved; by decreasing accumulated unobligated balances, an optimum level of resource utilization was to be attained by 1986. Second, procedures for the procurement of goods and services were to be streamlined in order to permit substantial increases in programme delivery. Third, systematic project evaluation was to lead to a number of specific actions that would increase the effectiveness of the Agency's development assistance. With regard to the first aim, implementation increased by 44% over the 1983 level, passing the $30 million mark in October and reaching $36.6 million by the end of the year. Of this amount, $31.8 million related to the implementation of activities programmed for 1984. Therefore, an increase in total resources of only 4% was accompanied by an increase in current-year implementation of 34%. As a result, the upward trend in the unobligated balance was checked, and earmarkings against the TACF actually decreased. The implementation rate against the TACF rose from 58% in 1983 to 65% in 1984, reaching the level that had been set as a target. If this performance can be maintained in 1985, it will be possible to reach the optimum level of TACF resource utilization one year earlier than originally expected. As regards the second aim, streamlined procedures introduced in

  17. Report on operation utilization and technical development of research reactors and hot laboratory

    International Nuclear Information System (INIS)

    1982-03-01

    Activities of the Division of Research Reactor Operation in fiscal 1980 are described. The division is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other works are performed, including technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, postirradiation examinations of fuels and materials are made, and also development of examination methods. (author)

  18. Report on operation, utilization and technical development of research reactors and hot laboratory

    International Nuclear Information System (INIS)

    1980-03-01

    Activities of the Division of Research Reactor Operation in fiscal 1978 are described. The division is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other works are performed, including technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, postirradiation examinations of fuels and materials are made, and also development of examination methods. (author)

  19. Tore Supra: technical aspects and early results after one year of operation

    International Nuclear Information System (INIS)

    Gravier, R.

    1989-01-01

    After one year operation (1988 to 1989), technical aspects of component systems and equipment of Tore Supra are summarized. Particular attention is given to the operation with: supraconducting toroidal field coil system, cryogenic system, poloidal field system, in vessel equipment, first wall conditioning, pump limiter. The ergodic divertor experiments and the current drive experiment are reported. The plasma heating methods adopted in Tore Supra are presented

  20. Report on operation, utilization and technical development of Research Reactors and Hot Laboratory

    International Nuclear Information System (INIS)

    1984-10-01

    Activities of the Division of Research Reactor Operation in fiscal 1981 are described. The division is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other works are performed, including technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, postirradiation examinations of fuels and materials are made, and also development of examination methods. (author)

  1. Design and Assessment of an Associate Degree-Level Plant Operations Technical Education Program

    Science.gov (United States)

    Selwitz, Jason Lawrence

    2017-01-01

    Research was undertaken to develop and evaluate an associate degree-level technical education program in Plant Operations oriented towards training students in applied science, technology, engineering, and mathematics (STEM) skills and knowledge relevant to a spectrum of processing industries. This work focuses on four aspects of the curriculum…

  2. Technical Diagnostics of Ventilation Units for Energy Efficiency and Safety of Operation

    Directory of Open Access Journals (Sweden)

    Kuzin Evgeny

    2017-01-01

    Full Text Available The article considers the questions of application of technical diagnostics fan installations methods for providing safe operation, the system of the technical maintenance improvement and repair. Due to the feet that one of the most important aspects in fan operation in mining is energy efficiency and energy saving, the lack of the data in the control of the level in vibration of stationary sensors is shown. The necessity of taking into account the geometric parameters of the intake channel has been shown, and also the necessity of creation of the reference masks for the assessment of technical condition and energy efficiency when operating fan installations in mining. The results of technical diagnostics of the main fans using the methods of vibration diagnostics are provided. Aspects of vibration at characteristic points are shown. The necessity for further accumulation of data characterizing vibration for adjustment of the reference masks and more accurate detection of defects and deviations from the energy-efficient mode of operation of the fan installations is given.

  3. The IAEA technical Co-operation a partner in development in Latin America

    Energy Technology Data Exchange (ETDEWEB)

    El-Saiedi, A [International Atomic Energy Agency, Vienna (Austria). Div. of Public Information

    1995-10-01

    Each country was to find means of achieving sustainable development, and for this, technology within a framework of regional and international co-operation are of utmost importance. The IAEA plays a major role in promoting nuclear technologies for development. Highlights of the IAEA`s technical cooperation programme are given in this paper.

  4. The IAEA technical Co-operation a partner in development in Latin America

    International Nuclear Information System (INIS)

    El-Saiedi, A.

    1995-01-01

    Each country was to find means of achieving sustainable development, and for this, technology within a framework of regional and international co-operation are of utmost importance. The IAEA plays a major role in promoting nuclear technologies for development. Highlights of the IAEA's technical cooperation programme are given in this paper

  5. Technical Diagnostics of Ventilation Units for Energy Efficiency and Safety of Operation

    Science.gov (United States)

    Kuzin, Evgeny; Shahmanov, Vitality; Dubinkin, Dmitriy

    2017-11-01

    The article considers the questions of application of technical diagnostics fan installations methods for providing safe operation, the system of the technical maintenance improvement and repair. Due to the feet that one of the most important aspects in fan operation in mining is energy efficiency and energy saving, the lack of the data in the control of the level in vibration of stationary sensors is shown. The necessity of taking into account the geometric parameters of the intake channel has been shown, and also the necessity of creation of the reference masks for the assessment of technical condition and energy efficiency when operating fan installations in mining. The results of technical diagnostics of the main fans using the methods of vibration diagnostics are provided. Aspects of vibration at characteristic points are shown. The necessity for further accumulation of data characterizing vibration for adjustment of the reference masks and more accurate detection of defects and deviations from the energy-efficient mode of operation of the fan installations is given.

  6. Technical co-operation report for 2002. Report by the Director General

    International Nuclear Information System (INIS)

    2003-08-01

    General Conference resolution GC(46)/RES/10 reiterated the need to strengthen the technical co- operation programme and requested the Director General to report to the Board of Governors periodically and to the General Conference at its forty-seventh (2003) session on the implementation of resolution GC(46)/RES/10. Part A of this report responds to the General Conference resolution by providing an overview of the progress achieved in technical co-operation policies, strategies, working relations, and internal management during the period 1 April 2002 to 31 March 2003, as well as the major new challenges facing the technical co-operation programme. Part B reports on operational activities and programme performance at the country and regional levels during the calendar year 2002, and Part C reviews the use of financial and human resources in the programme at an aggregate level. As part of its efforts to refine policies for improving programme development, the Agency reviewed the Technical Co-operation Strategy in 2002. The resulting document, The Technical Co-operation Strategy: the 2002 Review (document GOV/INF/2002/8/Mod.1), states that the strategic goal originally identified in the Strategy in 1997 remains valid, and defines four objectives to guide the technical co-operation programme: applying the central criterion (strong government commitment), developing strategic partnerships, increasing the level of funding for technical co-operation, and promoting greater sustainability and self-reliance of nuclear institutions. In line with the Technical Co-operation Strategy, one of the key features of the Agency.s work in 2002 was continuing consultations with Member States at both the policy and operational levels on the management of the ongoing technical co-operation programme and on planning for future activities. The dialogue with Member States aimed at clarifying the strategic objectives and key tools for the utilization of resources to achieve maximum

  7. The Agency's Technical Co-operation activities in 1987. Report by the Director General

    International Nuclear Information System (INIS)

    1988-08-01

    This report is part of a wide range of documentation which the Agency provides to Member States on its technical co-operation activities at various times during the year. It is, in particular, complemented by the achievement reporting submitted to the Technical Assistance and Co-operation Committee of the Board in the annual implementation reports that give the status of the technical co-operation programmes as at 30 September in each year. Following the 1986 Technical Co-operation Seminar and based on continuing consultations with Member States various steps to improve the quality of the programme were taken in 1987: for example, new project request forms and management plans were introduced and preparatory assistance was expanded. Office automation was intensified and the computerized data base covering technical co-operation was enhanced further. Work continues on the adaptation of data provided by the new Financial Information and Control System (FIGS) to the needs of the technical co-operation programmes and vice-versa. While several problems have still to be overcome, it has on the whole, been possible in this report to re-establish data comparability with previous years. Evaluation has become an integral part of the Agency's technical cooperation activities. In addition to on-going mid-project and end-of-project evaluations, expert services and fellowships were evaluated in 1987 and the first country programme evaluation was also undertaken. During 1987, a total of 962 projects were operational and 64 training courses were held. These activities involved 1808 expert assignments while 1975 persons received training abroad. Of the provisions in the 1987 total adjusted programme, one half was earmarked for equipment, while the other half was equally divided between ear markings for experts and for training. Of the Agency's technical co-operation resources in 1987, 72.5% came from the Technical Assistance and Co-operation Fund, 13.7% from extra budgetary

  8. Short-term energy outlook. Quarterly projections, first quarter 1995

    International Nuclear Information System (INIS)

    1995-02-01

    The Energy Information Administration (EIA) prepares quarterly, short-term energy supply, demand, and price projections for publication in February, May, August, and November in the Short-Term Energy Outlook (Outlook). The forecast period for this issue of the Outlook extends from the first quarter of 1995 through the fourth quarter of 1996. Values for the fourth quarter of 1994, however, are preliminary EIA estimates or are calculated from model simulations using the latest exogenous information available (for example, electricity sales and generation are simulated using actual weather data). The historical energy data, compiled into the first quarter 1995 version of the Short-Term Integrated Forecasting System (STIFS) database, are mostly EIA data regularly published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications. Minor discrepancies between the data in these publications and the historical data in this Outlook are due to independent rounding. The STIFS database is archived quarterly and is available from the National Technical Information Service. The cases are produced using the Short-Term Integrated Forecasting System (STIFS). The STIFS model is driven principally by three sets of assumptions or inputs: estimates of key macroeconomic variables, world oil price assumptions, and assumptions about the severity of weather. Macroeconomic estimates are produced by DRI/McGraw-Hill but are adjusted by EIA to reflect EIA assumptions about the world price of crude oil, energy product prices, and other assumptions which may affect the macroeconomic outlook. The EIA model is available on computer tape from the National Technical Information Service

  9. A technical system to improve the operational monitoring of the Zaporozhye nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Beyer, M; Carl, H; Nowak, K [Technischer Ueberwachungsverein Rheinland, Koeln (Germany). Inst. for Nuclear Engineering and Radiation Protection; Schumann, P; Seidel, A; Weiss, F P; Zschau, J

    1998-10-01

    As part of the programme implemented by the German Ministry of Environment, Nature Conservation and Reactor Safety to cooperate with the Central and Eastern European States (CEES) and the Commonwealth of Independent States (CIS) in the area of nuclear safety, a technical system to improve operational monitoring has been designed, specified and established since 1992 as a pilot project in the Zaporozhye/Ukraine nuclear power plant by Forschungszentrum Rossendorf and Technischer Ueberwachungsverein Rheinland with a significant contribution from the State Scientific and Technical Centre of the Ukrainian supervisory authority. The technical system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables a continuous monitoring of the state of unit 5 in normal operation and in cases of anomalies or incidents so that when recognisable deviations from the regular plant operation occur, the Ukrainian supervisory authority can immediately inquire and if necessary impose conditions on the operator. The radiological and meteorological parameters at the nuclear power plant location are monitored to the extent necessary to assess the current radiation situation and to implement efficient emergency management measures. (orig.)

  10. A technical system to improve the operational monitoring of the Zaporozhye nuclear power plant

    International Nuclear Information System (INIS)

    Beyer, M.; Carl, H.; Nowak, K.; Schumann, P.; Seidel, A.; Weiss, F.P.; Zschau, J.

    1998-01-01

    As part of the programme implemented by the German Ministry of Environment, Nature Conservation and Reactor Safety to cooperate with the Central and Eastern European States (CEES) and the Commonwealth of Independent States (CIS) in the area of nuclear safety, a technical system to improve operational monitoring has been designed, specified and established since 1992 as a pilot project in the Zaporozhye/Ukraine nuclear power plant by Forschungszentrum Rossendorf and Technischer Ueberwachungsverein Rheinland with a significant contribution from the State Scientific and Technical Centre of the Ukrainian supervisory authority. The technical system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables a continuous monitoring of the state of unit 5 in normal operation and in cases of anomalies or incidents so that when recognisable deviations from the regular plant operation occur, the Ukrainian supervisory authority can immediately inquire and if necessary impose conditions on the operator. The radiological and meteorological parameters at the nuclear power plant location are monitored to the extent necessary to assess the current radiation situation and to implement efficient emergency management measures. (orig.)

  11. Technical data for concentrated solar power plants in operation, under construction and in project

    Directory of Open Access Journals (Sweden)

    Ugo Pelay

    2017-08-01

    Full Text Available This article presents technical data for concentrated solar power (CSP plants in operation, under construction and in project all over the world in the form of tables. These tables provide information about plants (e.g., name of the CSP plant, country of construction, owner of the plant, aim of the plant and their technical characteristics (e.g., CSP technology, solar power, area of the plant, presence and type of hybridization system, electricity cost, presence and type of TES, power cycle fluid, heat transfer fluid, operating temperature, operating pressure, type of turbine, type and duration of storage, etc.. Further interpretation of the data and discussions on the current state-of-the-art and future trends of CSP can be found in the associated research article (Pelay et al., 2017 [1].

  12. On the issue of selecting technical and operational parameters for buses in urban passenger routes

    Directory of Open Access Journals (Sweden)

    Rudzinskyi V.V.

    2017-10-01

    Full Text Available Problems of a public transport bus service in urban areas were analyzed. The aim of the article is to determine actual operational parameters of buses during passenger transportation in Zhytomyr. Ways of determining technical and operational parameters of buses were developed using visual and tabular methods of city buses real-time speed and acceleration performance registration by GPS-monitoring system with the help of a communicational and informational intelligent transport system of the city. Experimental studies of city buses motion parameters were presented. A comprehensive survey of passenger traffic and conditions of public transport functioning in Zhytomyr was carried out. The values of technical and operational parameters of buses on city routes were obtained. Preliminarily conclusions and recommendations considering the criteria for selecting the optimal rolling stock for a bus network of the city were suggested.

  13. Technical co-operation report for 1998. Report by the Director General

    International Nuclear Information System (INIS)

    1999-01-01

    This report presents the IAEA Technical Co-operation (TC) activities during 1998 and highlights most significant accomplishments. Part I of this report reviews the strengthening of TC, both in financial aspects and through implementation of the TC strategy. Part II reviews extensively the actual output of the TC programme; it looks at each geographic region, and reports on the results of national, regional and, where applicable, interregional activities in those regions. Part III presents a technical discussion of the financial parameters of the TC programme and ends with financial implementation summaries

  14. Technical co-operation report for 1998. Report by the Director General

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    This report presents the IAEA Technical Co-operation (TC) activities during 1998 and highlights most significant accomplishments. Part I of this report reviews the strengthening of TC, both in financial aspects and through implementation of the TC strategy. Part II reviews extensively the actual output of the TC programme; it looks at each geographic region, and reports on the results of national, regional and, where applicable, interregional activities in those regions. Part III presents a technical discussion of the financial parameters of the TC programme and ends with financial implementation summaries.

  15. Design and Assessment of an Associate Degree-Level Plant Operations Technical Education Program

    Science.gov (United States)

    Selwitz, Jason Lawrence

    Research was undertaken to develop and evaluate an associate degree-level technical education program in Plant Operations oriented towards training students in applied science, technology, engineering, and mathematics (STEM) skills and knowledge relevant to a spectrum of processing industries. This work focuses on four aspects of the curriculum and course development and evaluation research. First, the context of, and impetus for, what was formerly called vocational education, now referred to as technical or workforce education, is provided. Second, the research that was undertaken to design and evaluate an associate degree-level STEM workforce education program is described. Third, the adaptation of a student self-assessment of learning gains instrument is reviewed, and an analysis of the resulting data using an adapted logic model is provided, to evaluate the extent to which instructional approaches, in two process control/improvement-focused courses, were effective in meeting course-level intended learning outcomes. Finally, eight integrative multiscale exercises were designed from two example process systems, wastewater treatment and fast pyrolysis. The integrative exercises are intended for use as tools to accelerate the formation of an operator-technician's multiscale vision of systems, unit operations, underlying processes, and fundamental reactions relevant to multiple industries. Community and technical colleges serve a vital function in STEM education by training workers for medium- and high-skilled technical careers and providing employers the labor necessary to operate and maintain thriving business ventures. Through development of the curricular, course, and assessment-related instruments and tools, this research helps ensure associate degree-level technical education programs can engage in a continual process of program evaluation and improvement.

  16. 48{sup th} Annual meeting on nuclear technology (AMNT 2017). Key topic / Enhanced safety and operation excellence. Technical session: Operation and safety of nuclear installations, fuel

    Energy Technology Data Exchange (ETDEWEB)

    Hollands, Thorsten [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany). Bereich Reaktorsicherheitsforschung

    2017-12-15

    The sessions Fuel and Materials and Containment and SFP, as part of the Technical Sessions Operation and Safety of Nuclear Installations, Fuel implemented in the Key Topic Enhanced Safety and Operation Excellence were chaired by Dr. Thorsten Hollands (Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH) and Dr. Erwin Fischer (PreussenElektra GmbH) who was the keynote coordinator for the Technical Sessions. Both sessions consist of a keynote lecture followed by technical presentations.

  17. Hazardous materials in aquatic environments of the Mississippi River Basin Project management. Technical quarterly progress report, April 1, 1996--June 30, 1996

    Energy Technology Data Exchange (ETDEWEB)

    McLachlan, J.; Ide, C.F.; O`Connor, S.

    1996-08-01

    This quarterly report summarizes accomplishments for the Project examining hazardous materials in aquatic environments of the Mississippi River Basin. Among the many research areas summarized are the following: assessment of mechanisms of metal-induced reproductive toxicity in aquatic species as a biomarker of exposure; hazardous wastes in aquatic environment;ecological sentinels of aquatic contamination in the lower Mississippi River System; remediation of selected contaminants; rapid on-site immunassay for heavy metal contamination; molecular mechanisms of developmental toxicity induced by retinoids and retinoid-like molecules; resuseable synthetic membranes for the removal of aromatic and halogenated organic pollutants from waste water; Effects of steroid receptor activation in neurendocrine cell of the mammalian hypothalamus; modeling and assessment of environmental quality of louisiana bayous and swamps; enhancement of environmental education. The report also contains a summary of publications resulting from this project and an appendix with analytical core protocals and target compounds and metals.

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

    International Nuclear Information System (INIS)

    1993-01-01

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

  19. Technical Co-operation Report for 1996. Report by the Director General

    International Nuclear Information System (INIS)

    1997-01-01

    The Agency's Technical Cooperation (TC) Programme made further progress during 1996 in implementing recent initiatives to strengthen efficiency and effectiveness. These initiatives seek to maximize the developmental contribution of counterpart institutions by emphasizing the management of technology to solve social and economic problems. The new direction has been embodied in the term ''Partners in Development''. The Partners in Development approach is reflected in last year's Report to the Board of Governors and the General Conference on Strengthening of the Agency's Technical Co-operation Activities, which provided an update on ongoing activities and elaborated new initiatives. The 1995 Technical Cooperation Report focused on the progress in implementing these initiatives. Next year, the Secretariat plans to combine the TC Report with the Report on Strengthening of the Agency's Technical Co-operation Activities in order to improve the clarity, consistency and economy of these presentations. Establishing a development partnership with Member States is the central goal of a new Strategy for TC. The refinement of this strategy required considerable effort during 1996, when the process first began to define objectives, targets and the means of accomplishing them. Alongside internal consultations, the role of SAGTAC became instrumental in reaching consensus on the main elements of the strategy. Future efforts include the formulation of implementation plans for the strategy. Once completed, the strategy will be presented to the TACC and Board in 1997. Reflecting these developments, section A of this Report presents the basic features of the TC Strategy, and the approach to be taken to achieve its objectives. The Strategy addresses among others the recommendations contained in resolution GC(40)/RES/13 on the Strengthening of Technical Co-operation: activities to improve the scientific and technological capabilities of developing countries; to achieve sustainable

  20. Ten years's reactor operation at the Technical University Zittau - operation report

    International Nuclear Information System (INIS)

    Konschak, K.

    1990-01-01

    The Zittau Training and Research Reactor ZLFR is in use for purposes of teaching the engineers who will operate the nuclear power plants in the GDR since 10 years. Since commissioning it was started up more than 1600 times, approximately two thirds of the start-ups being utilized for purposes of teaching. A number of teaching experiments were installed that demonstrate fundamental technological processes in nuclear reactors in a manner easy to understand. The high level of nuclear safety manifests itself, among other things, in extremely low radiation exposures of the operating personal and the persons to be trained. (author)

  1. Technical co-operation report for 2001. Report by the Director General

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    Using nuclear technology as an effective tool for development is the challenge faced by the Agency's technical co-operation programme. This was the subject of the 4th IAEA Scientific Forum, entitled 'Nuclear technology for sustainable development: serving human needs,' which was held in conjunction with the 45th General Conference in September 2001. Opening the Forum, Professor Jeffrey Sachs of Harvard University emphasized the importance of developing mechanisms to mobilize science and technology to meet the growing challenge of serving human needs in a sustainable manner and commended the Agency for its achievements in this regard. This report provides information on how the technical co-operation programme has responded to that challenge over the past year. One of the highlights of the technical co-operation programme in 2001 was the launching of the Pan-African Tsetse and Trypanosomosis Eradication Campaign (PATTEC) in Ouagadougou, Burkina Faso, in October. This represented the culmination of years of effort by African Member States, working in partnership with the Agency and the Organization for African Unity (OAU), and was an important milestone in the progress of applying the sterile insect technique (SIT) to the area-wide eradication of the tsetse fly in Africa. It is a good example of how science and technology can contribute to socio-economic development with a direct impact at the community level. The level of Member States' pledges to the Technical Co-operation Fund (TCF) for 2001, more than $59 million, was the second highest ever. This represented a rate of attainment of 80.01% (as of 31 March 2002), thus achieving the target set by the General Conference for that year. The extra budgetary contributions, more than $7 million, were the highest in ten years. These contributions, together with payments of assessed programme costs and other income, meant that total new resources for the year reached $71.1 million. In December 2000, the Board approved an

  2. Technical co-operation report for 2001. Report by the Director General

    International Nuclear Information System (INIS)

    2001-01-01

    Using nuclear technology as an effective tool for development is the challenge faced by the Agency's technical co-operation programme. This was the subject of the 4th IAEA Scientific Forum, entitled 'Nuclear technology for sustainable development: serving human needs,' which was held in conjunction with the 45th General Conference in September 2001. Opening the Forum, Professor Jeffrey Sachs of Harvard University emphasized the importance of developing mechanisms to mobilize science and technology to meet the growing challenge of serving human needs in a sustainable manner and commended the Agency for its achievements in this regard. This report provides information on how the technical co-operation programme has responded to that challenge over the past year. One of the highlights of the technical co-operation programme in 2001 was the launching of the Pan-African Tsetse and Trypanosomosis Eradication Campaign (PATTEC) in Ouagadougou, Burkina Faso, in October. This represented the culmination of years of effort by African Member States, working in partnership with the Agency and the Organization for African Unity (OAU), and was an important milestone in the progress of applying the sterile insect technique (SIT) to the area-wide eradication of the tsetse fly in Africa. It is a good example of how science and technology can contribute to socio-economic development with a direct impact at the community level. The level of Member States' pledges to the Technical Co-operation Fund (TCF) for 2001, more than $59 million, was the second highest ever. This represented a rate of attainment of 80.01% (as of 31 March 2002), thus achieving the target set by the General Conference for that year. The extra budgetary contributions, more than $7 million, were the highest in ten years. These contributions, together with payments of assessed programme costs and other income, meant that total new resources for the year reached $71.1 million. In December 2000, the Board approved an

  3. Technical Condition of Earthen Dams at Nizhegorodskaya HPP After 60 Years of Operation

    Energy Technology Data Exchange (ETDEWEB)

    Kuznetsov, V. S., E-mail: kuznetsovVS@vniig.ru; Ladenko, S. Yu., E-mail: ladenko@yandex.ru [B. E. Vedeneev All-Russian Research Institute of Hydraulic Engineering (JSC) (Russian Federation)

    2016-03-15

    The complex of hydraulic engineering installations includes five earthen dams. All facilities are of Class I. The diagnostic parameters of dam operation and technical condition monitored via in-situ observation for seepage mode, seepage strength, settlement, static stability, etc. generally meet design assumptions and safety criteria. Despite individual defects and signs of “aging” identified over the period of earthen dam operation, these are currently in a satisfactory and operable state. The long, 60-year operating period of the dams with no serious overhauls or emergencies has demonstrated the high reliability of the facilities, the correctness of the design and technological solutions adopted and implemented in the construction, and the high professional level of their operation in close cooperation with science.

  4. Annual report on operation, utilization and technical development of research reactors and hot laboratory

    International Nuclear Information System (INIS)

    1990-09-01

    This report describes the activities of the Department of Research Reactor Operation in fiscal year of 1989. It also presents some technical topics on the reactor operation and utilization in details. The Department is responsible for operation of the research reactors, JRR-2 and JRR-4, and the Hot Laboratory. The research reactor JRR-3 was reconstructed to enhance the performance for utilization. The first criticality was achieved on March 22, 1989, and it subsequently went into operation. In connection with the reactor operation, the various research and development activities in the area of fuel management, water chemistry, radiation monitoring and material irradiation have been made. In the Hot Laboratory, post-irradiation examinations of fuels and materials have been carried out along with the development of related techniques. (author)

  5. Technical and operational organisation of the 'Swiss Marketplace': GridCode CH

    International Nuclear Information System (INIS)

    Imhof, K.; Baumann, R.

    2001-01-01

    This article describes the minimum requirements placed on the operators of electricity grids by the planned Swiss Electricity Market Law. These are compiled in the Swiss Grid Code - GridCode CH. The various players in an open electricity market such as generating companies, power brokers, those responsible for balance groups, grid operators, system co-ordinators, the operators of fine distribution networks and the final consumer and the roles they play are examined. The history of the development of the Grid Code, which contains technical and operational regulations for the successful co-operation of the market players, is reviewed. The contractual obligations of the partners involved and, in particular, regulations concerning metering, measured value designation and the provision of data are discussed

  6. Technical co-operation report for 1999. Report by the Director General

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-08-01

    This report presents the IAEA Technical Co-operation (TC) activities in 1999 and covers three separate topics. Part I reports on the Strengthening of TC and looks at the elements of the TC Strategy and how they contributed to the TC Programme. Part II reports on the major achievements of the TC Programme in 1999 in different regions of the world. In addition to reviewing some of the results of national and regional activities in each region - including activities under Regional Co-operation Agreements - this section looks at three interregional projects, and provides highlights of selected projects that were closed in 1999. Part III presents a technical discussion of the financial parameters of the TC Programme. A more detailed review of resources and contributions, disbursements, and non-financial indicators is provided in a Supplement to this report.

  7. Technical co-operation report for 1999. Report by the Director General

    International Nuclear Information System (INIS)

    2000-08-01

    This report presents the IAEA Technical Co-operation (TC) activities in 1999 and covers three separate topics. Part I reports on the Strengthening of TC and looks at the elements of the TC Strategy and how they contributed to the TC Programme. Part II reports on the major achievements of the TC Programme in 1999 in different regions of the world. In addition to reviewing some of the results of national and regional activities in each region - including activities under Regional Co-operation Agreements - this section looks at three interregional projects, and provides highlights of selected projects that were closed in 1999. Part III presents a technical discussion of the financial parameters of the TC Programme. A more detailed review of resources and contributions, disbursements, and non-financial indicators is provided in a Supplement to this report

  8. EVALUATING THE OVERALL TECHNICAL EFFICIENCY OF ISLAMIC BANKS OPERATING IN THE MENA REGION DURING THE FINANCIAL CRISIS.

    Directory of Open Access Journals (Sweden)

    Ali Said

    2013-04-01

    Full Text Available The present paper measured overall technical efficiency of Islamic banks operating in the MENA region during the financial crisis of 2007-2009 to address the question what are the levels of overall, pure technical and scale efficiency of Islamic banks operating in the MENA region and how they evolved during the financial crisis. This paper addresses this question technical, pure technical, and scale efficiency measures are analyzed by employing on-parametric technique, Data Envelopment Analysis (DEA. The study results suggested that Islamic banks in other MENA countries and North Africa on an average are relatively technically inefficient. This might be due to the underdeveloped banking system in those countries. In addition, the decomposition of technical efficiency into pure technical and scale efficiency shows that on average, the Islamic banks in North Africa counties and other MENA counties are having problems in the allocation of resources between their inputs and outputs mix compare to Islamic banks in GCC.

  9. MATHEMATICAL MODELS OF PROCESSES AND SYSTEMS OF TECHNICAL OPERATION FOR ONBOARD COMPLEXES AND FUNCTIONAL SYSTEMS OF AVIONICS

    Directory of Open Access Journals (Sweden)

    Sergey Viktorovich Kuznetsov

    2017-01-01

    Full Text Available Modern aircraft are equipped with complicated systems and complexes of avionics. Aircraft and its avionics tech- nical operation process is observed as a process with changing of operation states. Mathematical models of avionics pro- cesses and systems of technical operation are represented as Markov chains, Markov and semi-Markov processes. The pur- pose is to develop the graph-models of avionics technical operation processes, describing their work in flight, as well as during maintenance on the ground in the various systems of technical operation. The graph-models of processes and sys- tems of on-board complexes and functional avionics systems in flight are proposed. They are based on the state tables. The models are specified for the various technical operation systems: the system with control of the reliability level, the system with parameters control and the system with resource control. The events, which cause the avionics complexes and func- tional systems change their technical state, are failures and faults of built-in test equipment. Avionics system of technical operation with reliability level control is applicable for objects with constant or slowly varying in time failure rate. Avion- ics system of technical operation with resource control is mainly used for objects with increasing over time failure rate. Avionics system of technical operation with parameters control is used for objects with increasing over time failure rate and with generalized parameters, which can provide forecasting and assign the borders of before-fail technical states. The pro- posed formal graphical approach avionics complexes and systems models designing is the basis for models and complex systems and facilities construction, both for a single aircraft and for an airline aircraft fleet, or even for the entire aircraft fleet of some specific type. The ultimate graph-models for avionics in various systems of technical operation permit the beginning of

  10. Regular pipeline maintenance of gas pipeline using technical operational diagnostics methods

    Energy Technology Data Exchange (ETDEWEB)

    Volentic, J [Gas Transportation Department, Slovensky plynarensky priemysel, Slovak Gas Industry, Bratislava (Slovakia)

    1998-12-31

    Slovensky plynarensky priemysel (SPP) has operated 17 487 km of gas pipelines in 1995. The length of the long-line pipelines reached 5 191 km, distribution network was 12 296 km. The international transit system of long-line gas pipelines ranged 1 939 km of pipelines of various dimensions. The described scale of transport and distribution system represents a multibillion investments stored in the ground, which are exposed to the environmental influences and to pipeline operational stresses. In spite of all technical and maintenance arrangements, which have to be performed upon operating gas pipelines, the gradual ageing takes place anyway, expressed in degradation process both in steel tube, as well as in the anti-corrosion coating. Within a certain time horizon, a consistent and regular application of methods and means of in-service technical diagnostics and rehabilitation of existing pipeline systems make it possible to save substantial investment funds, postponing the need in funds for a complex or partial reconstruction or a new construction of a specific gas section. The purpose of this presentation is to report on the implementation of the programme of in-service technical diagnostics of gas pipelines within the framework of regular maintenance of SPP s.p. Bratislava high pressure gas pipelines. (orig.) 6 refs.

  11. Regular pipeline maintenance of gas pipeline using technical operational diagnostics methods

    Energy Technology Data Exchange (ETDEWEB)

    Volentic, J. [Gas Transportation Department, Slovensky plynarensky priemysel, Slovak Gas Industry, Bratislava (Slovakia)

    1997-12-31

    Slovensky plynarensky priemysel (SPP) has operated 17 487 km of gas pipelines in 1995. The length of the long-line pipelines reached 5 191 km, distribution network was 12 296 km. The international transit system of long-line gas pipelines ranged 1 939 km of pipelines of various dimensions. The described scale of transport and distribution system represents a multibillion investments stored in the ground, which are exposed to the environmental influences and to pipeline operational stresses. In spite of all technical and maintenance arrangements, which have to be performed upon operating gas pipelines, the gradual ageing takes place anyway, expressed in degradation process both in steel tube, as well as in the anti-corrosion coating. Within a certain time horizon, a consistent and regular application of methods and means of in-service technical diagnostics and rehabilitation of existing pipeline systems make it possible to save substantial investment funds, postponing the need in funds for a complex or partial reconstruction or a new construction of a specific gas section. The purpose of this presentation is to report on the implementation of the programme of in-service technical diagnostics of gas pipelines within the framework of regular maintenance of SPP s.p. Bratislava high pressure gas pipelines. (orig.) 6 refs.

  12. The Agency's technical co-operation programme with Thailand 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Thailand carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  13. The Agency's technical co-operation programme with Sri Lanka 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Sri Lanka carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  14. The Agency's technical co-operation programme with Bolivia 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Bolivia carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  15. The Agency's technical co-operation programme with Panama 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Panama carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  16. The Agency's technical co-operation programme with Bangladesh 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Bangladesh carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  17. The Agency's technical co-operation programme with Panama 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Panama carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  18. The Agency's technical co-operation programme with Guatemala 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Guatemala carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  19. The Agency's technical co-operation programme with Iceland 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Iceland carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  20. The Agency's technical co-operation programme with Bangladesh 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Bangladesh carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  1. The Agency's technical co-operation programme with Cyprus 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Cyprus carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  2. The Agency's technical co-operation programme with Albania 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Albania carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  3. The Agency's technical co-operation programme with Indonesia 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Indonesia carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  4. The Agency's technical co-operation programme with Poland 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Poland carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  5. The Agency's technical co-operation programme with Romania 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Romania carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  6. The Agency's technical co-operation programme with Viet Nam 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Viet Nam carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  7. The Agency's technical co-operation programme with the Philippines 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Philippines carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  8. The Agency's technical co-operation programme with The Philippines 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in The Philippines carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  9. The Agency's technical co-operation programme with Greece 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Greece carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  10. The Agency's technical co-operation programme with Dominican Republic 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Dominican Republic carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  11. The Agency's technical co-operation programme with Nicaragua 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Nicaragua carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  12. The Agency's technical co-operation programme with Afghanistan 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Afghanistan carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  13. The Agency's technical co-operation programme with Jamaica 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Jamaica carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  14. The Agency's technical co-operation programme with Ecuador 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Ecuador carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  15. The Agency's technical co-operation programme with El Salvador 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in El Salvador carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  16. The Agency's technical co-operation programme with Nigeria 1986-1996 country programme summaries

    International Nuclear Information System (INIS)

    1996-01-01

    This report contains a review of the Agency's technical co-operation activities in Nigeria carried out during 1986-1996. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  17. The Agency's technical co-operation programme with Bolivia 1986-1996 country programme summaries

    International Nuclear Information System (INIS)

    1996-01-01

    This report contains a review of the Agency's technical co-operation activities in Bolivia carried out during 1986-1996. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  18. Use of experience for the improvement of technical specifications for operation

    International Nuclear Information System (INIS)

    Schweitz, J.P.; Seveon, J.J.

    1987-11-01

    The lessons drawn from experience led EdF to define in 1980 a national specification standard, to be applied to the first standardized series of 900 MWe units and to be adapted to the later 1300 MWe units. This document is periodically revised, every two years or so, to take into account new trends in safety thinking and lessons learnt from operating experience. In this paper we present the main developments in the field of technical specifications, particularly: the definition of rules applicable in the event of unavailability of safety-related equipment, the integration of plant unit operating feedback for specifications optimization

  19. The Agency's technical co-operation programme with Colombia 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Colombia carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  20. The Agency's technical co-operation programme with Portugal 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Portugal carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  1. The Agency's technical co-operation programme with Pakistan 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Pakistan carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  2. Technical co-operation report for 1997. Report by the Director General

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-08-01

    This report covers the IAEA Technical Co-operation (TC) activities during 1997, gives examples of the most significant accomplishments during the year and sets out the status of resources and delivery of the TC programme. The document outlines the steps taken to strengthen planning, design, monitoring and evaluation of TC projects. It also describes how the programme's operational base is being broadened to form new partnerships, using Country Programme Frameworks and Thematic Planning to meet the Member States' priority needs and expand project impact.

  3. Technical co-operation report for 1997. Report by the Director General

    International Nuclear Information System (INIS)

    1998-08-01

    This report covers the IAEA Technical Co-operation (TC) activities during 1997, gives examples of the most significant accomplishments during the year and sets out the status of resources and delivery of the TC programme. The document outlines the steps taken to strengthen planning, design, monitoring and evaluation of TC projects. It also describes how the programme's operational base is being broadened to form new partnerships, using Country Programme Frameworks and Thematic Planning to meet the Member States' priority needs and expand project impact

  4. The Agency's technical co-operation programme with Myanmar 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Myanmar carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  5. The Agency's technical co-operation programme with Malaysia 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Malaysia carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  6. The Agency's technical co-operation programme with Jordan 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Jordan carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  7. The Agency's technical co-operation programme with Mongolia 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Mongolia carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  8. The Agency's technical co-operation programme with Egypt 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Egypt carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  9. The Agency's technical co-operation programme with Paraguay 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Paraguay carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  10. The Agency's technical co-operation programme with Mexico 1986-1996 country programme summaries

    International Nuclear Information System (INIS)

    1996-01-01

    This report contains a review of the Agency's technical co-operation activities in Mexico carried out during 1986-1996. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  11. The Agency's technical co-operation programme with Paraguay 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Paraguay carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  12. The Agency's technical co-operation programme with Hungary 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in Hungary carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  13. Post waterflood CO{sub 2} miscible flood in light oil fluvial dominated deltaic reservoirs. Second quarterly technical progress report, [January 1, 1995--March 31, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    Production from the Marg Area 1 at Port Neches is averaging 392 barrels of oil per day (BOPD) for this quarter. The production drop is due to fluctuation in both GOR and BS&W on various producing well, coupled with low water injectivity in the reservoir. We were unable to inject any tangible amount of water in the reservoir since late January. Both production and injection problems are currently being evaluated to improve reservoir performance. Well Kuhn (No. 6) was stimulated with 120 MMCF of CO{sub 2}, and was placed on production in February 1, 1995. The well was shut in for an additional month after producing dry CO{sub 2} initially. The well was opened again in early April and is currently producing about 40 BOPD. CO{sub 2} injection averaged 11.3 MMCFD including 4100 MMCFD purchased from Cardox, while water injection averaged 1000 BWPD with most of the injection occurring in the month of January.

  14. Direct synthesis of 2-methyl-1-propanol/methanol fuels and feedstocks: Quarterly technical progress report for the period June--August 1985

    Energy Technology Data Exchange (ETDEWEB)

    Klier, K.; Herman, R. G.; Simmons, G. W.; Nunan, J.; Himelfarb, P. B.

    1985-09-01

    During the present quarter, and intensive series of aluminum- supported catalysts, both Cs promoted and unpromoted, have been prepared by a special preparation technique and tested to determine alcohol synthesis activity, selectivities, and stability. Preparation of a single-phase hydrotalcite-like ((Cu/sub x/Zn/sub 1 -x/)/sub 6/Al/sub 2/CO/sub 3/(OH)/sub 16//center dot/4H/sub 2/O) catalyst precursor has been successfully accomplished. Some of these catalysts have been tested to determine their activities in producing methanol and higher alcohols. It has been observed that catalysts obtained by calcination and reduction of the hydrotalcite-like precursor are very active methanol synthesis catalysts. Doping these catalysts with cesium in an aqueous solution leads to initial deactivation, which is partially recovered by doping at higher cesium levels. Results give us guidelines for altering the promoter doping procedure so that a more active and selective aluminum-supported higher alcohol synthesis catalyst will be obtained. 4 refs., 13 figs., 13 tabs.

  15. Risk-based configuration control: Application of PSA in improving technical specifications and operational safety

    International Nuclear Information System (INIS)

    Samanta, P.K.; Kim, I.S.; Vesely, W.E.

    1992-01-01

    Risk-based configuration control is the management of component configurations using a risk perspective to control risk and assure safety. A configuration, as used here, is a set of component operability statuses that define the state of a nuclear power plant. If the component configurations that have high risk implications do not occur, then the risk from the operation of nuclear power plants would be minimal. The control of component configurations, i.e., the management of component statuses, to minimize the risk from components being unavailable, becomes difficult, because the status of a standby safety system component is often not apparent unless it is tested. Controlling plant configuration from a risk-perspective can provide more direct risk control and also more operational flexibility by allowing looser controls in areas unimportant to risk. Risk-based configuration control approaches can be used to replace parts of nuclear power plant Technical Specifications. With the advances in probabilistic safety assessment (PSA) technology, such approaches to improve Technical Specifications and operational safety are feasible. In this paper, we present an analysis of configuration risks, and a framework for risk-based configuration control to achieve the desired control of risk-significant configurations during plant operation

  16. Unusual occurrences during LMFR operation. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2000-10-01

    Design of liquid metal cooled fast reactors (LMFRs) is still in evolution, and only a small number of LMFRs are in operation around the world. Specialists operating these LMFRs have gained valuable experience from incidents, failures, and other events that took place in the reactors. These unusual occurrences, lessons learned and measures undertaken to prevent recurrences are often either not reported in the literature, or reported only briefly and without sufficient detail. Hence there is a need for specialists designing and operating LMFRs to share their knowledge on unusual occurrences. Considerable experimental and theoretical knowledge in this field were collected by several Member states over the past decades. The needs in generalisation, review and documentation of fundamental knowledge in liquid metal cooled reactor technology were a major consideration in the recommendation by the International Working group on fast reactors for the IAEA to convene this Technical Committee meeting on the subject of unusual occurrences during LMFR operation and the consequences for reactor systems

  17. The Agency's Technical Co-operation programme with Kenya, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With almost $3.9 million of Agency support received, Kenya ranks 39th among all recipients of technical assistance during the period 1958-1991. Almost half of the assistance during the past ten years has been provided in the form of the equipment (44%), followed by training (33%) and expert services (23%). Two-thirds of the funds available were provided by the Technical Assistance and Co-operation Fund (66%), while extra-budgetary contributions accounted for 18%, in-kind contributions for 14%, and UNDP for 2% of the resources. With regard to project disbursements during the past ten years, by sector, the four major areas have been general atomic energy development (30%), agriculture (22%), nuclear medicine and nuclear safety (13% each)

  18. The Agency's Technical Co-operation programme with Niger, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With some $1.5 million of Agency support received, Niger ranks 65th among all recipients of technical assistance in the period 1958 through 1991. About two-thirds of the assistance received during the past ten years has been provided in the form of equipment (62%), complemented by expert services (26%) and training (12%). Almost the entire resources utilized were provided by the Technical Assistance and Co-operation Fund (96%), with only a small share made available through assistance in kind (4%). With regard to project disbursements by sector, the four major areas have been agriculture (34%), general atomic energy development (31%), hydrology (18%) and nuclear safety (12%)

  19. The Agency's Technical Co-operation programme with Sierra Leone, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $1.1 million of Agency support received, Sierra Leone ranks 70th among all recipients of technical assistance in the period 1958 through 1991. Almost equal shares of the assistance during the past ten years have been provided in the form of equipment (40%) and expert services (37%), while the share of the training component was 23%. The best part of the resources was provided by the Technical Assistance and Co-operation Fund (96%), the remaining 4% was made available through assistance in kind. During the past ten years, project activities - and disbursements - have concentrated exclusively on three major areas: nuclear medicine (52%), general atomic energy development (25%) and agriculture (23%)

  20. The Agency's Technical Co-operation programme with Cameroon, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $1.3 million of Agency support received, Cameroon ranks 68th among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance received during the past ten years has been provided in the form of equipment (61%), followed by expert services (24%) and training (15%). The best part of the resources were provided by the Technical Assistance and Co-operation Fund (90%); the remaining ten per cent were made available through extrabudgetary contributions (8%) and assistance in kind (2%). With regard to project disbursements by sector, the four major areas have been nuclear physics and chemistry (38%), agriculture (23%), nuclear medicine (14%) and hydrology (13%)

  1. The Agency's Technical Co-operation programme with Mali, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $2.7 million of Agency support received, Mali ranks 51st among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (58%), followed by expert services (27%) and training (15%). With a share of 93%, the Technical Assistance and Co-operation Fund has provided the best part of the resources, while only very small shares were made available through extrabudgetary contributions and assistance in kind (5% and 2%, respectively). With regard to project disbursements during the past ten years, by sector, the four major areas have been hydrology (31%), nuclear medicine (24%), agriculture (21%) and nuclear raw materials (16%)

  2. The Agency's Technical Co-operation programme with Costa Rica, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $2.8 million of Agency support received, Costa Rica ranks 49th among all recipients of technical assistance in the period 1958-1991. Over half of the assistance during the past ten years has been provided in the form of equipment (52%), followed by expert services (37%) and training (11%). Sixty-two per cent of the resources were made available through the Technical Assistance and Co-operation Fund, while 37% of the resources were provided by UNDP. The rest was made available through extrabudgetary contributions (5%) and through in-kind assistance (1%). With regard to project disbursement by sector, the largest areas have been nuclear raw materials (36%), nuclear physics and chemistry (24%) and agriculture (20%). Smaller shares have gone to hydrology (11%) and nuclear medicine (8%)

  3. The Agency's Technical Co-operation programme with Zambia, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $5.5 million of Agency support received, Zambia ranks 33rd among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (61%), followed by expert services (25%) and training (14%). Almost all of the resources made available came from the Technical Assistance and Co-operation Fund (93%), with only very small shares provided through extrabudgetary contributions (4%) and assistance in kind (3%). With regard to project disbursements during the past ten years, by sector, the largest areas have been agriculture (33%) and general atomic energy development (23%), followed by industry and hydrology (19%), nuclear raw materials (13%) and nuclear safety (6%)

  4. The Agency's Technical Co-operation programme with Algeria, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $3.6 million of Agency support received, Algeria ranks 41st among all recipients of technical assistance in the period 1958-1991. Seventy per cent of the assistance received during the past ten years has been in the form of equipment, followed by expert services (17%) and training (13%). Almost all of the resources were provided by the Technical Assistance and Co-operation Fund (97%), the remaining 3% were made available through assistance in kind. With regard to project disbursement by sector, the three major areas have been nuclear physics and chemistry (28%), agriculture (27%) and nuclear medicine (20%)

  5. The Agency's Technical Co-operation programme with Ethiopia, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With some $2.5 million of Agency support received, Ethiopia ranks 54th among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance received during the past ten years has been provided in the form of equipment (55%), complemented by expert services (16%) and training (29%). The best part of the resources was provided by the Technical Assistance and Co-operation Fund (88%), the remainder was made available through assistance in kind (6%), UNDP and extrabudgetary contributions (3% each). During the past ten years, project disbursements went to four major areas: agriculture (45%), nuclear medicine (35%), nuclear safety (14%) and nuclear engineering and technology (6%)

  6. The Agency's Technical Co-operation programme with Mexico, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With almost $7.7 million of Agency support received, Mexico ranks 21st among all recipients of technical assistance during the period 1958 through 1991. The largest share of the assistance received during the past ten years has been in the form of expert services (36%), followed by equipment and training (27% each) and sub-contracts (10%). Almost two-thirds of the funds available were provided by the Technical Assistance and Co-operation Fund (65%), the rest was made available through extrabudgetary contributions (21%) and assistance in kind (14%). With regard to project disbursements during the past ten years, by sector the five major areas have been nuclear safety (34%), nuclear engineering and technology (27%), agriculture (17%), nuclear physics and chemistry (9%), and nuclear techniques in industry and hydrology (9%)

  7. The Agency's Technical Co-operation programme with Uganda, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $1.6 million of Agency support received, Uganda ranks 61st among all recipients of technical assistance in the period 1958 through 1991. Almost half of the assistance received during the past ten years has been provided in the form of equipment (47%), complemented by a strong training component (37%), while expert services have received only a relatively small share (16%). Ninety-eight per cent of the resources were provided by the Technical Assistance and Co-operation Fund, the remaining two per cent were made available through assistance in kind. During the past ten years, project activities - and disbursements - have concentrated exclusively on three major areas: agriculture (64%), nuclear medicine (24%) and nuclear safety (12%)

  8. The Agency's Technical Co-operation programme with Uruguay, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $4.2 million of Agency support received, Uruguay ranks 37th among all recipients of technical assistance in the period 1958 - 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (67%), followed by expert services (19%) and training (14%). Seventy-three per cent of the resources were provided through the Technical Assistance and Co-operation Fund, while 24% were made available through extrabudgetary contributions. The remaining 3% were provided through assistance in kind, with only an insignificant contribution by UNDP. With regard to project disbursement by sector, the largest areas have been nuclear medicine (35%), agriculture (23%), general atomic energy development (17%), followed by nuclear physics and chemistry (11%) and industry and hydrology (7%)

  9. The Agency's technical co-operation activities in 1985. Report by the Director General

    International Nuclear Information System (INIS)

    1986-08-01

    Although total resources and disbursements were higher in 1985 than in previous years, the growth rates for both declined somewhat. New resources for the Technical Assistance and Co-operation Fund (TACF) increased by 13%, the TACF accounting for over 66% of all technical co-operation resources in 1985. Pledges made towards the 1985 target for voluntary contributions to the TACF came close to 90% of the target. Although a significant loss on exchange had to be absorbed by the Fund, 96.9% of the target was covered thanks to additional income. Although extrabudgetary resources declined in 1985, they still accounted for one fifth of all technical assistance resources. There was a significant increase in in-kind contributions; this was attributable to the support for non-destructive testing training in Latin America given by Canada, which was the second largest donor of in-kind assistance after the United States. UNDP resources rose very slightly. With UNDP's new five-year programming cycle beginning in 1987, there may be further increases if new projects are identified and timely action taken. New information on implementation expressed as net expenditure and net expenditure rates has been introduced in the form of Expenditure Summaries I, II and III, which provide a more precise picture of performance by fund, geographic area, programme component, field of activity and technical Division. Net expenditure against all funds stood at 57.9%. Net expenditure against the TACF was 66.3%. As UNDP resources and funds in trust account for relatively small shares of the programme, their utilization does not influence the overall net expenditure rate significantly. However, the slow utilization of extrabudgetary resources did have an adverse effect on programme performance as a whole. Net expenditures from the TACF continued to increase at a higher rate than resources, so that the unobligated balance declined for the second consecutive year. In the past, the growing unobligated

  10. The Agency's Technical Co-operation programme with Nigeria, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $9.3 million of Agency support received, Nigeria ranks 14th among all recipients of technical assistance in the period 1958 through 1991. During the past ten years, 44% of this assistance has been provided in the form of equipment, followed by training (27%), expert services (26%) and sub-contracts (3%). With 45% and 44%, respectively, the Technical Assistance and Co-operation Fund and extrabudgetary contributions hold almost equal shares in the total resources made available, while in-kind assistance accounts for 9% and UNDP for 2% of the resources. With regard to project disbursement during the past ten years, by sector, by far the largest area has been agriculture (70%), with significantly smaller shares going to nuclear physics and chemistry (11%), nuclear medicine (8%) and nuclear safety (7%)

  11. The Agency's Technical Co-operation programme with Senegal, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With $2.2 million of Agency support received, Senegal ranks 56th among all recipients of technical assistance in the period 1958 - 1991. More than one-third of the assistance during the past ten years has been provided in the form of equipment (67%), followed by expert services (21%) and training (12%). Eighty per cent of the resources were provided by the Technical Assistance and Co-operation Fund, while 16% were made available by UNDP and about 2% each through extrabudgetary contributions and assistance in kind. With regard to project disbursement by sector, by far the largest area has been agriculture (43%). Smaller shares have gone to general atomic energy development (15%), nuclear physics and chemistry (13%), nuclear medicine and hydrology (11% each), and nuclear safety (7%)

  12. Practical operation of technical department plants for the determination of the efficiency of bio gas according to the regulation VDI 4630; Praxisbetrieb von Technikumsanlagen zur Biogaspotenzialbestimmung gemaess VDI-Richtlinie 4630

    Energy Technology Data Exchange (ETDEWEB)

    Nelles, M.; Banemann, D.; Engler, N. [Univ. Rostock (Germany). Inst. fuer Umweltingenieurwesen; Fritz, T. [HAWK, FH Hildesheim Holzminden Goettingen (Germany). Fachgebiet Technischer Umweltschutz; Ramhold, D. [IS Forschungsgesellschaft mbH (Germany)

    2007-07-01

    For the operation of biological gas facilities, the practice-orientated determination of gas yields is of great importance regarding to the input. The University of Rostock (Rostock, Federal Republic of Germany) and the University of Applied Sciences and Arts (Hildesheim, Federal Republic of Germany) developed the GRW procedure (GRW = Goettingen, Rostock, Wahlstedt) for the determination of yields of bio gas. The pilot plant successfully is operated for two years in Goettingen. Since the midth of 2006, a further plant runs at the research association of the Schaumann group in Wahlstedt (Federal Republic of Germany) in the course of a research co-operation. At present, a further developed plant is built in the new refuse economy technical school and bio energy technical department at the University of Rostock. The operation is taken up in the fourth quarter of the year 2007. The authors of the contribution under consideration report on the methodology, the practice-oriented conversion and results from the operation of the plants in the bio gas technical department.

  13. The Agency's Technical Co-operation activities in 1986. Report by the Director General

    International Nuclear Information System (INIS)

    1987-08-01

    During 1986, a total of 854 projects were operational and 71 training courses were held. These activities involved 1930 expert assignments. In addition, 937 persons received training under the fellowship programme. Performance indicators (non-financial) are given in Part II of this report (Sections B and C) in order to provide some impression of the increase in implementation actions related to the delivery of a growing programme. Although total resources were higher in 1986 than in previous years, the overall growth rate declined further while new obligations and disbursements increased steeply. The near-stagnation in the net expenditure rate for Technical Assistance and Co-operation Fund (TACF) resources which occurred in 1985 prompted close monitoring and follow-up measures in 1986. These actions led to an all-time high TACF net expenditure rate, namely 75.7%, in 1986. As the TACF represented 71% of all technical co-operation resources, overall programme performance in terms of net expenditure reached 67.6%, which is also the highest rate ever recorded. TACF resources increased by 11%. Pledges and miscellaneous income covered 92.7% of the target. The percentage attainment of the target has been declining since 1983. As actual disbursements against the TACF increased at a much higher rate than new resources, the unobligated balance decreased to the extent that striving for even higher net expenditure rates would no longer be consistent with judicious resource management. The share of extrabudgetary funds in the programme declined: they accounted for 14.5% of the resources and 12.6% of the disbursements in 1986. The Federal Republic of Germany became the largest contributor of extrabudgetary funds. Special attention will be given to the utilization of these resources so that delivery rates can be improved. As anticipated, UNDP's share in resources and disbursements increased and several new large-scale projects were approved. In-kind assistance continued to play a

  14. A systematic assessment of the state of hazardous waste clean-up technologies. Quarterly technical progress report, April 1--June 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Berg, M.T.; Reed, B.E.; Gabr, M.

    1993-07-01

    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 Report for Year 1 of the Agreement. This report reflects the progress and/or efforts performed on the following nine technical projects encompassed by the Year 1 Agreement for the period of April 1 through June 30, 1993: Systematic assessment of the state of hazardous waste clean-up technologies; site remediation technologies -- drain-enhanced soil flushing (DESF) for organic contaminants removal; site remediation technologies -- in situ bioremediation of organic contaminants; excavation systems for hazardous waste sites; chemical destruction of polychlorinated biphenyls; development of organic sensors -- monolayer and multilayer self-assembled films for chemical sensors; Winfield lock and dam remediation; Assessments of Technologies for hazardous waste site remediation -- non-treatment technologies and pilot scale test facility implementation; and remediation of hazardous sites with stream reforming.

  15. 72201 - Temporary reduction of resources for technical infrastructure (TI) operation (ex TCR)

    CERN Multimedia

    Peter Sollander

    2005-01-01

    For a period of two years starting on 1 April 2005, the technical infrastructure will be supervised by a single TI operator rather than two. Initially, this operator will not be able to leave the control room for on-site interventions. Only stand-by staff will be available for breakdown repairs and, as a result, intervention times outside normal working hours are liable to increase. Response times on the 72201 phone number may similarly increase. All requests for breakdown repairs may be sent to the new e-mail address: service-ti@cern.ch; the old address - tcr@cern.ch - will stay in operation. Thank you for your understanding. Peter Sollander AB/OP/TI

  16. Flight Technical Error Analysis of the SATS Higher Volume Operations Simulation and Flight Experiments

    Science.gov (United States)

    Williams, Daniel M.; Consiglio, Maria C.; Murdoch, Jennifer L.; Adams, Catherine H.

    2005-01-01

    This paper provides an analysis of Flight Technical Error (FTE) from recent SATS experiments, called the Higher Volume Operations (HVO) Simulation and Flight experiments, which NASA conducted to determine pilot acceptability of the HVO concept for normal operating conditions. Reported are FTE results from simulation and flight experiment data indicating the SATS HVO concept is viable and acceptable to low-time instrument rated pilots when compared with today s system (baseline). Described is the comparative FTE analysis of lateral, vertical, and airspeed deviations from the baseline and SATS HVO experimental flight procedures. Based on FTE analysis, all evaluation subjects, low-time instrument-rated pilots, flew the HVO procedures safely and proficiently in comparison to today s system. In all cases, the results of the flight experiment validated the results of the simulation experiment and confirm the utility of the simulation platform for comparative Human in the Loop (HITL) studies of SATS HVO and Baseline operations.

  17. Draft Function Allocation Framework and Preliminary Technical Basis for Advanced SMR Concepts of Operations

    Energy Technology Data Exchange (ETDEWEB)

    Hugo, Jacques [Idaho National Lab. (INL), Idaho Falls, ID (United States); Forester, John [Idaho National Lab. (INL), Idaho Falls, ID (United States); Gertman, David [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey [Idaho National Lab. (INL), Idaho Falls, ID (United States); Medema, Heather [Idaho National Lab. (INL), Idaho Falls, ID (United States); Persensky, Julius [Idaho National Lab. (INL), Idaho Falls, ID (United States); Whaley, April [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2013-08-01

    This report presents preliminary research results from the investigation into the development of new models and guidance for Concepts of Operations in advanced small modular reactor (AdvSMR) designs. AdvSMRs are nuclear power plants (NPPs), but unlike conventional large NPPs that are constructed on site, AdvSMRs systems and components will be fabricated in a factory and then assembled on site. AdvSMRs will also use advanced digital instrumentation and control systems, and make greater use of automation. Some AdvSMR designs also propose to be operated in a multi-unit configuration with a single central control room as a way to be more cost-competitive with existing NPPs. These differences from conventional NPPs not only pose technical and operational challenges, but they will undoubtedly also have regulatory compliance implications, especially with respect to staffing requirements and safety standards.

  18. Environmental Restoration (ER) Consolidated Quarterly Report_April to June 2017_ October 2017

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-10-01

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

  19. Performance of operating and advanced light water reactor designs. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-10-01

    Nuclear power can provide security of energy supply, stable energy costs, and can contribute to greenhouse gas reduction. To fully realize these benefits, a continued and strong focus must be maintained on means for assuring the economic competitiveness of nuclear power relative to alternatives. Over the past several years, considerable improvements have been achieved in nuclear plant performance. Worldwide, the average energy availability factor has increased from 66 per cent in 1980 to 81 per cent in 1999, with some utilities achieving significantly higher values. This is being achieved through integrated programmes including personnel training and quality assurance, improvements in plant system and component design and plant operation, by various means to reduce outage duration for maintenance and refuelling and other scheduled shutdowns, and by reducing the number of forced outages. Application of technical means for achieving high performance of nuclear power plants is an important element for assuring their economic competitiveness. For the current plants, proper management includes development and application of better technologies for inspection, maintenance and repair. For future plants, the opportunity exists during the design phase to incorporate design features and technologies for achieving high performance. This IAEA Technical Committee meeting (TCM) provided a forum for information exchange on design features and technologies incorporated into LWR plants commissioned within the last 15-20 years, and into evolutionary LWR designs still under development, for achieving performance improvements with due regard to stringent safety requirements and objectives. It also addressed on-going technology development expected to achieve further improvements and/or significant cost reductions. The TCM was attended by 32 participants from 14 Member States: Argentina, Bulgaria, Czech Republic, Finland, France, Germany, Hungary, Japan, Republic of Korea, Mexico

  20. Safe operation of critical assemblies and research reactors. Code of practice and Technical appendix. 1971 ed

    International Nuclear Information System (INIS)

    Cox, J.

    1971-01-01

    This book is in two parts. The first is a Code of Practice for the Safe Operation of Critical Assemblies and Research Reactors, prepared as a result of a meeting of experts which took place in Vienna on 20-24 May 1968. The Code has been prepared by the International Atomic Energy Agency in co-operation with the World Health Organization, and its publication is sponsored by both organizations. In addition, the Code was approved by the Board of Governors of the International Atomic Energy Agency on 16 December 1968 as part of the Agency's safety standards, which are applied to operations undertaken by Member States with the assistance of the Agency. The Board, in approving the publication of the present book, also recommended Member States to take the Code into account in the formulation of national regulations and recommendations. The second part of the book is a Technical Appendix to give information and illustrative samples that would be helpful in implementing the Code of Practice. This second part, although published under the same cover, is not part of the Code. An extensive Bibliography, amplifying the Technical Appendix, is included at the end.

  1. A methodology for the analysis and selection of alternatives for the disposition of surplus plutonium. Quarterly technical progress report, April 1, 1995--June 30, 1995

    International Nuclear Information System (INIS)

    Mulder, R.

    1995-01-01

    The Office of Fissile Materials Disposition is currently involved in the development of a comprehensive approach to the long-term storage and disposition of fissile materials. A major objective of this effort is to provide a framework for US efforts to prevent the proliferation of nuclear weapons. This will entail both the elimination of excess highly enriched uranium and plutonium, and the insurance of the highest standards of safety, security, and international accountability. The Office of Fissile Materials Disposition is supporting an Interagency Working Group that has initiated a comprehensive review of alternatives for plutonium disposition which takes into account non-proliferation, economic, technical, institutional, schedule, environmental, and health and safety issues. These alternatives were identified by the development of screening criteria as a guide to the selection of alternatives that best achieve the fissile nuclear material long-term storage and disposition goals of the US Government

  2. The Agency's Technical Co-operation programme in Chile, 1981-1991. Country programme evaluation

    International Nuclear Information System (INIS)

    1992-01-01

    Agency support for nuclear activities in Chile dates back to the early 1960s. During the last ten years, the period covered by this evaluation, this support has considerably expanded. In the period 1981-1991, 62 Agency projects with allotments amounting to over $7 million were completed or are under implementation. Through this co-operation Chile has received 360 man-months of expert services, $3.4 million worth of equipment, and 105 fellowships for some 390 man-months of training. In addition, 262 Chileans attended 219 Agency regional and interregional training courses, and Chilean institutions were awarded 40 research contracts worth over $325,000. This evaluation covers ten years of Agency technical co-operation with Chile, during which 35 projects were completed and 27 are still being implemented. Eight major sectors received assistance: general atomic energy development; nuclear physics; nuclear raw materials; nuclear engineering and technology; nuclear techniques in agriculture; nuclear medicine; hydrology; and nuclear safety. The evaluation concluded that, overall, the Agency's technical co-operation activities have, in keeping with the national priorities concerning peaceful nuclear applications, contributed substantially to the establishment of Chile's nuclear scientific and technical infrastructure, and played a major role in Chile's efforts to introduce nuclear applications in a number of sectors of the economy, with many benefits for broader national development objectives. Another strength of the Agency's programme with Chile is the high level of commitment and dedication that was noted in the great majority of recipient institutions, and in particular at the Comision Chilena de Energia Nuclear, CChEN. Mention should also be made of the fact that bureaucracy appears to be less severe than in some other developing countries, and that constraints that frequently affect other countries, such as insufficient counterpart commitment and lack of continuity of

  3. Environmental-technical aspects of the operation of the accelerator at NIKHEF-K

    International Nuclear Information System (INIS)

    Post, J.C.

    1982-12-01

    This report discusses those technical aspects of the operation of the Medium Energy Accelerator at NIKHEF-K which affect the environment. The accelerator produces an electron beam with a maximum capacity of 300 kW and, as by-products, intense gamma and neutron radiations. These radiations can contaminate components of the accelerator and the direct surroundings. The electron beam can also generate ozone in the air. The accelerator produces a small quantity of radioactive waste itself and research in the chemistry department also leads to the production of radioactive waste. These wastes are stored temporarily and transported for treatment/storage elsewhere in Holland once a year. (Auth.)

  4. High Burnup Fuel: Implications and Operational Experience. Proceedings of a Technical Meeting

    International Nuclear Information System (INIS)

    2016-08-01

    This publication reports on the outcome of a technical meeting on high burnup fuel experience and economics, held in Buenos Aires, Argentina in 2013. The purpose of the meeting was to revisit and update the current operational experience and economic conditions associated with high burnup fuel. International experts with significant experience in experimental programmes on high burnup fuel discussed and evaluated physical limitations at pellet, cladding and structural component levels, with a wide focus including fabrication, core behaviour, transport and intermediate storage for most types of commercial nuclear power plants

  5. Technical Aspect for Operating Portable Prompt Gamma Neutron Activation Analysis (PGNAA) on Terengganu Inscribed Stone

    International Nuclear Information System (INIS)

    Rasif Mohd Zain; Hearie Hassan; Roslan Yahya

    2015-01-01

    Prompt Gamma Neutron Activation analysis (PGNAA) is a type of neutron activation analysis which can determined element with nearly no gamma ray decay after being irradiated by neutron sourced. Thus, element that cannot be determined by the conventional NAA for example H, B, N, Si and Cd, can be determine by PGNAA. This paper focuses on the technical working procedure for operating portable PGNAA in field work. The device is designed as a portable non-destructive investigation tool applying an isotopic neutron source (Cf-252) and a gamma-ray spectroscopy system for in-situ investigation. The studied have been carried out on Terengganu inscribed stone at Terengganu State Museum. (author)

  6. The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency. Latest Status

    International Nuclear Information System (INIS)

    1979-03-01

    The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency were approved by the Board of Governors on 21 February 1979. The test is reproduced herein for the information of all Members. The provisions established by the Board of Governors on 24 September 1977 for the application of safeguards in relation to the granting of technical assistance are also reproduced in the Annex to the Revised Guiding Principles and General Operating Rules.

  7. IAEA's technical co-operation programme and its role in assisting member states in the safe utilisation of nuclear power

    International Nuclear Information System (INIS)

    Reed, J.

    2000-01-01

    In this contribution the author deals with the technical co-operation projects of the IAEA. The Agency's technical co-operation programme is a most welcome mechanism for the transfer of nuclear technology, and to developing countries it is certainly the most attractive side of the Agency, since it is through this programme that the IAEA can contribute to the solution of their problems through the provision of know-how, technology and training. (authors)

  8. 10 CFR 34.69 - Records of quarterly inventory.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Records of quarterly inventory. 34.69 Section 34.69 Energy... INDUSTRIAL RADIOGRAPHIC OPERATIONS Recordkeeping Requirements § 34.69 Records of quarterly inventory. (a) Each licensee shall maintain records of the quarterly inventory of sealed sources and of devices...

  9. Geothermal space/water heating for Mammoth Lakes Village, California. Quarterly technical progress report, 13 December 1976-12 March 1977

    Energy Technology Data Exchange (ETDEWEB)

    Sims, A.V.; Racine, W.C.

    1977-01-01

    During the second three months of this feasibility study to determine the technical, economic and environmental feasibility of heating Mammoth Lakes Village, California using geothermal energy, the following work was accomplished. A saturation survey of the number and types of space and water heaters currently in use in the Village was completed. Electric energy and ambient temperature metering equipment was installed. Peak heating demand for Mammoth Lakes was estimated for the years 1985, 1990 and 2000. Buildings were selected which are considered typical of Mammoth Lakes in terms of their heating systems to be used in estimating the cost of installing hydronic heating systems in Mammoth. Block diagrams and an order of magnitude cost comparison were prepared for high-temperature and low-temperature geothermal district heating systems. Models depicting a geothermal district heating system and a geothermal-electric power plant were designed, built and delivered to ERDA in Washington. Local input to the feasibility study was obtained from representatives of the State of California Departments of Transportation and Fish and Game, US Forest Service, and Mono County Planning Department.

  10. Operation of a semi-technical pilot plant for nuclear aided steam gasification of coal

    International Nuclear Information System (INIS)

    Kirchhoff, R.; Heek, K.H. van; Juentgen, H.; Peters, W.

    1984-01-01

    After intensive investigations on a small scale, the principle of the process has been tested in a semi-technical pilot plant. In its gasifier a fluidized bed of approx. 1 m 2 cross-section and of up to 4 m height is operated at 40 bar. Heat is supplied to the bed from an immersed heat exchanger with helium flowing through it, which is heated electrically. The plant was commissioned in 1976 and has been in hot operation for approx. 23000 h, over 13000 h whereof account for coal gasification. Roughly 1600 t of coal have been put through. During recent years the processing of German caking long-flame gas coal and the marked improvement of the process by the use of catalysts have been demonstrated successfully. (orig.)

  11. Glass melter materials technical options for the French vitrification process and operations experience authors

    International Nuclear Information System (INIS)

    Bonniaud, R.; Roznad, L.; Demay, R.

    1986-09-01

    The French vitrification process for solidifying high-level radioactive waste which has been under industrial application since 1978, is mentioned briefly. This technique involves glass melting at 1,150 deg.C, using an induction heated metallic vessel. The molten glass pouring is controlled by a thermal gate, which is also heated by induction. Two types of vessel are in use. Both are remotely removable and disposable to permit replacement at regular intervals. The technical criteria (the materials used have to meet) are described. The behaviour of the materials has been investigated using the industrial experience gained in the AVM facility during 8 years of operation, as well as with operation of a prototype for the new vitrification facilities under construction at La Hague. A short description of the use of these materials is also presented

  12. Steady state operation of tokamaks. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2000-10-01

    The first IAEA Technical Committee Meeting (TCM) on Steady State Operation of Tokamaks was organized to discuss the operations of present long-pulse tokamaks (TRIAM-1M, TORE SUPRA, MT-7, HT-7M, HL-1M) and the plans for future steady-state tokamaks such as SST-1, CIEL, and HT-7U. This meeting, held from 13-15 October 1998, was hosted by the Academia Sinica Institute of Plasma Physics (ASIPP), Hefei, China. Participants from China, France, India, Japan, the Russian Federation, and the IAEA participated in the meeting. There were 18 individual presentations plus general discussions on many topics, including superconducting magnet systems, cryogenics, plasma position control, non-inductive current drive, auxiliary heating, plasma-wall interactions, high heat flux components, particle control, and data acquisition

  13. NRC quarterly [status] report

    International Nuclear Information System (INIS)

    1987-01-01

    This report covers the third quarter of calendar year 1987. The NRC licensing activity during the period of this report included the issuance of a full-power license for Beaver Valley 2 on August 14, 1987, and operating license restricted to five percent power for South Texas Unit 1 on August 21, 1987. Additional licensing delay for Shoreham is projected due to complex litigation. Also, licensing delay may occur for Comanche Peak Unit 1, because the duration of the hearing is uncertain. Although a license authorizing fuel loading and precriticality testing for Seabrook Unit 1 has been issued, there is a projected delay for low-power licensing. Full-power licensing for Seabrook Unit 1 will be delayed due to offsite emergency preparedness issues. The length of the delay is not known at this time. With the exception of Seabrook and Shoreham, regulatory delays in this report are not impacted by the schedules for resolving off-site emergency preparedness issues

  14. Technical challenges in the qualitative ecological risk assessments performed on the Hanford Site operable units

    International Nuclear Information System (INIS)

    Probasco, K.M.

    1994-01-01

    Qualitative Risk Assessments (QRAS) have been selected as the method for providing the risk-driver indications for interim, remedial, and cleanup actions for the Hanford Site operable units' ecological risk assessments. This expedited response action path has been developed for the Hanford Site to facilitate time-critical decisions and generate immediate emergency cleanup actions. Tight budgets and aggressive time schedules are a major factor in the development of the QRA process. The QRA is a quick way to find immediate threats and a good precursor to a full risk assessment. However, numerous technical challenges have been identified with the QRA approach. The QRA approach differs from a baseline risk assessment in several ways. The main differences involve the use of data that have previously been gathered from the site, and the development of a ''bias-for-action'' document that would reveal qualitative risks from the contaminants identified at the operable units. Technical challenges concerning the ecological portion of these QRAs have raised questions about using the ORA for decision-making and may have weakened the validity of its use in the established procedural framework. Challenges involving such issues as the extrapolation of the contaminant data, data validation and screening techniques, receptor selections, and the final risk characterization outcome threaten the feasibility of the QRA as a decision-making tool. This discussion provides insight into resolving technical challenges and may be a ''lessons-learned'' device for those interested in the QRA approach. Ultimately, these challenges are proving to be learning tools for scientists, regulators, and ecologists and are identifying the data gaps and research direction for future ecological baseline risk assessments

  15. Manpower development for safe operation of nuclear power plant. China. Seminar on the technical support functions. Activity: 6.1.1-Task-03. Technical report

    International Nuclear Information System (INIS)

    Kofron, K.L.

    1994-01-01

    The seminar was held in Wuhan PRC from 01.10/94 - 01/14/94. It revolved about the role of the Technical Support Groups, both onsite and offsite, of the Nuclear Power Plant. This was to assist the Chinese in deciding their best course of action for the establishment and operation of this group

  16. Summary of Tiger Team Assessment and Technical Safety Appraisal recurring concerns in the Operations Area

    International Nuclear Information System (INIS)

    1993-01-01

    Fourteen Tiger Team Assessment and eight Technical Safety Appraisal (TSA) final reports have been received and reviewed by the DOE Training Coordination Program during Fiscal Year 1992. These assessments and appraisals included both reactor and non-reactor nuclear facilities in their reports. The Tiger Team Assessments and TSA reports both used TSA performance objectives, and list ''concerns'' as a result of their findings. However, the TSA reports categorized concerns into the following functional areas: (1) Organization and Administration, (2) Radiation Protection, (3) Nuclear Criticality Safety, (4) Occupational Safety, (5) Engineering/Technical Support, (6) Emergency Preparedness, (7) Safety Assessments, (8) Quality Verification, (9) Fire Protection, (10) Environmental Protection, and (11) Energetic Materials Safety. Although these functional areas match most of the TSA performance objectives, not all of the TSA performance objectives are addressed. For example, the TSA reports did not include Training, Maintenance, and Operations as functional areas. Rather, they included concerns that related to these topics throughout the 11 functional areas identified above. For consistency, the Operations concerns that were identified in each of the TSA report functional areas have been included in this summary with the corresponding TSA performance objective

  17. Technically-oriented operation management systems in conjunction with commercial DB systems

    Energy Technology Data Exchange (ETDEWEB)

    Lex, M.; Heselmann, B. [GiS mbH, Erlangen (Germany); Eschbach, P. [BASF Consult GmbH, Muenchen (Germany)

    2001-07-01

    Due to the liberalization of the electricity market, the efficiency and competitiveness of a power plant is increasingly measured at the cost per amount of energy generated. Thus, aspects of market-orientation and clearly cheaper electricity generation are in the foreground. Technically-oriented DP systems are necessary to save operating cost. These systems have structures differing from the mere business-oriented systems, because of the different frame conditions and operators' desire to stand out against rivalling competitors by technical and organizational measures. (orig.) [German] Die Effektivitaet und damit Konkurrenzfaehigkeit eines Kraftwerkes wird mit der Liberalisierung des Strommarktes verstaerkt an den Kosten je erzeugter Energieeinheit gemessen. Fuer den Betrieb ruecken damit Aspekte einer marktgerechten und somit deutlich kostenguenstigeren Stromerzeugung verstaerkt in den Vordergrund. Wer Betriebskosten sparen will, braucht technisch orientierte DV-Systeme, die aufgrund der unterschiedlichen Rahmenbedingungen und des Wunsches aller Anlagenbetreiber, sich durch technisch-organisatorische Massnahmen vom Wettbewerb vorteilhaft abzuheben, voellig andere Strukturen aufweisen als die betriebswirtschaftlich orientierten Systeme. (orig.)

  18. The Agency's Technical Co-operation programme with Brazil, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $17 million of Agency support received, Brazil ranks 2nd among all recipients of technical assistance during the period 1958 through 1991. Over half of the assistance received during the past ten years has been provided in the form of equipment (51%), complemented by expert services (34%) and training (15%). Almost two-thirds of the funds were made available through the Technical Assistance and Co-operation Fund (63%), the rest was provided through extrabudgetary contributions (30%), assistance in kind (4%) and UNDP (3%). With regard to total disbursements - by sector - under those projects that were operational during the period 1982 through November 1992, the three major areas have been: general atomic energy development (47%), nuclear safety (22%) and agriculture (13%). During the same period, the country has provided experts and training course lectures for a total of 405 assignments, and has hosted 178 fellowships and scientific visits as well as 46 regional and interregional training events with a total of 603 participants

  19. Evaluation of using cyclocranes to support drilling & production of oil & gas in wetland areas. Sixth quarterly technical progress report, incorporating milestone schedule/status, October 1993--December 1993

    Energy Technology Data Exchange (ETDEWEB)

    Eggington, W.J.

    1994-04-01

    This report is a progress report on a planned program falling under wetlands area research related to drilling, production, and transportation of oil and gas resources. Specifically the planned program addresses an evaluation of using cyclocraft to transport drill rigs, mud, pipes and other materials and equipment in a cost effective and environmentally safe manner to support oil and gas drilling and production operations in wetland areas. During this period, task 5, subscale tests, and task 7, environmental impacts, were completed. Work was continued on task 10, technology transfer, and the preparation of the final report as part of task 11.

  20. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1976

    International Nuclear Information System (INIS)

    Ferguson, J.B.

    1977-04-01

    Light water reactor safety research performed October through December 1976 is discussed. An analysis to determine the effect of emergency core coolant (ECC) injection location and pump speed on system response characteristics was performed. An analysis to evaluate the capability of commonly used critical heat flux (CHF) correlations to calculate the time of the first CHF in the Semiscale core during a loss-of-coolant experiment (LOCE) was performed. A test program and study to determine the effect thermocouples mounted on the outside fuel rod surfaces would have on the departure from nucleate boiling (DNB) phenomena in the LOFT core during steady state operation were completed. A correlation for use in predicting DNB heat fluxes in the LOFT core was developed. Tests of an experimental transit time flowmeter were completed. A nuclear test was performed to obtain fuel rod behavior data from four PWR-type rods during film boiling operation representative of PWR conditions. Preliminary results from the postirradiation examination of Test IE-1 fuel rods are given. Results of Irradiation Effects Tests IE-2 and IE-3 are given. Gap Conductance Test GC 2-1 was performed to evaluate the effects of fuel density, initial gap width, and fill gas composition on the pellet-cladding gap conductance

  1. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1976

    Energy Technology Data Exchange (ETDEWEB)

    Ferguson, J. B. [ed.

    1977-04-01

    Light water reactor safety research performed October through December 1976 is discussed. An analysis to determine the effect of emergency core coolant (ECC) injection location and pump speed on system response characteristics was performed. An analysis to evaluate the capability of commonly used critical heat flux (CHF) correlations to calculate the time of the first CHF in the Semiscale core during a loss-of-coolant experiment (LOCE) was performed. A test program and study to determine the effect thermocouples mounted on the outside fuel rod surfaces would have on the departure from nucleate boiling (DNB) phenomena in the LOFT core during steady state operation were completed. A correlation for use in predicting DNB heat fluxes in the LOFT core was developed. Tests of an experimental transit time flowmeter were completed. A nuclear test was performed to obtain fuel rod behavior data from four PWR-type rods during film boiling operation representative of PWR conditions. Preliminary results from the postirradiation examination of Test IE-1 fuel rods are given. Results of Irradiation Effects Tests IE-2 and IE-3 are given. Gap Conductance Test GC 2-1 was performed to evaluate the effects of fuel density, initial gap width, and fill gas composition on the pellet-cladding gap conductance.

  2. Safe Operation of Nuclear Power Plants. Code of Practice and Technical Appendices

    International Nuclear Information System (INIS)

    1969-01-01

    This book is in two parts. The first is a Code of Practice for the Safe Operation of Nuclear Power Plants and the second part is a compilation of technical appendices. Its object is to give information and illustrative examples that would be helpful in implementing the Code of Practice. This second part, although published under the same cover, is not part of the Code. Safe operation of a nuclear power plant postulates suitable siting and proper design, construction and management of the plant. Under the present Code of Practice for the Safe Operation of Nuclear Power Plants, those intending to operate the plant are recommended to prepare documentation which would deal with its operation and include safety analyses. The documentation in question would be reviewed by a regulatory body independent of the operating organization; operation would be authorized on the understanding that it would comply with limits and conditions designed to ensure safety. The Code may be subject to revision in the light of experience. The Appendices provide additional information together with some examples relating to certain topics dealt with in the Code; it must be emphasized that they are included as examples for information only and are not part of any recommendation. Purpose and scope: The recommendations in the Code are designed to protect the general public and the operating personnel from radiation hazards, and the Code forms part of the Agency's Safety Standards. The Code, which should be used in conjunction with the Agency's other Safety Standards, provides guidance and information to persons and authorities responsible for the operation of stationary nuclear power plants whose main function is the generation of thermal, mechanical or electrical power; it is not intended to apply to reactors used solely for experimental or research purposes. It sets forth minimum requirements which, it is believed, in the light of experience, must be met in order to achieve safe operation of a

  3. Idaho National Laboratory Quarterly Occurrence Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-11-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 85 reportable events (18 from the 4th Qtr FY-15 and 67 from the prior three reporting quarters), as well as 25 other issue reports (including events found to be not reportable and Significant Category A and B conditions) identified at INL during the past 12 months (8 from this quarter and 17 from the prior three quarters).

  4. Observation of behavioural markers of non-technical skills in the operating room and their relationship to intra-operative incidents.

    Science.gov (United States)

    Siu, Joey; Maran, Nikki; Paterson-Brown, Simon

    2016-06-01

    The importance of non-technical skills in improving surgical safety and performance is now well recognised. Better understanding is needed of the impact that non-technical skills of the multi-disciplinary theatre team have on intra-operative incidents in the operating room (OR) using structured theatre-based assessment. The interaction of non-technical skills that influence surgical safety of the OR team will be explored and made more transparent. Between May-August 2013, a range of procedures in general and vascular surgery in the Royal Infirmary of Edinburgh were performed. Non-technical skills behavioural markers and associated intra-operative incidents were recorded using established behavioural marking systems (NOTSS, ANTS and SPLINTS). Adherence to the surgical safety checklist was also observed. A total of 51 procedures were observed, with 90 recorded incidents - 57 of which were considered avoidable. Poor situational awareness was a common area for surgeons and anaesthetists leading to most intra-operative incidents. Poor communication and teamwork across the whole OR team had a generally large impact on intra-operative incidents. Leadership was shown to be an essential set of skills for the surgeons as demonstrated by the high correlation of poor leadership with intra-operative incidents. Team-working and management skills appeared to be especially important for anaesthetists in the recovery from an intra-operative incident. A significant number of avoidable incidents occur during operative procedures. These can all be linked to failures in non-technical skills. Better training of both individual and team in non-technical skills is needed in order to improve patient safety in the operating room. Copyright © 2014 Royal College of Surgeons of Edinburgh (Scottish charity number SC005317) and Royal College of Surgeons in Ireland. Published by Elsevier Ltd. All rights reserved.

  5. Idaho National Laboratory Quarterly Occurrence Analysis for the 1st Quarter FY2017

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-01-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 82 reportable events (13 from the 1st quarter (Qtr) of fiscal year (FY) 2017 and 68 from the prior three reporting quarters), as well as 31 other issue reports (including events found to be not reportable and Significant Category A and B conditions) identified at INL during the past 12 months (seven from this quarter and 24 from the prior three quarters).

  6. Idaho National Laboratory Quarterly Occurrence Analysis 4th Quarter FY 2016

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-11-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System, as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 84 reportable events (29 from the 4th quarter fiscal year 2016 and 55 from the prior three reporting quarters), as well as 39 other issue reports (including events found to be not reportable and Significant Category A and B conditions) identified at INL during the past 12 months (two from this quarter and 37 from the prior three quarters).

  7. Soil treatment to remove uranium and related mixed radioactive heavy metal contaminants. Ninth quarterly technical and financial progress report, January 1, 1995--March 31, 1995

    International Nuclear Information System (INIS)

    1995-05-01

    The objective of this project is to design and develop a physico-chemical treatment process for the removal of uranium and heavy metals from contaminated soil to achieve target contamination levels below 35 pCi/g of soil and a target for non-radioactive heavy metals below concentration levels permissible for release of the soil. The work will involve bench-scale and pilot-scale tests, using chelation-flotation, chemical leaching and ultrasonic leaching techniques, in conjunction with cross-flow microfiltration and filter-press operations. The effectiveness of an integrated process to treat leachates generated from soil processing will be demonstrated. Process flow-sheets suitable for in-situ and ex-situ applications will be developed and preliminary costs will be provided for the soil and leachate treatment technologies. In accordance with 10CFR 600.31 (d)(i), an extension of the project period including final report submission to 31 July 1995 was made in anticipation of potential delays in receiving Fernald soil samples at Chalk River Laboratories for the planned pilot-scale verification tests. Ex-situ pilot-scale soil decontamination and leachate treatment tests using Chalk River Chemical Pit soil are nearing completion. Soil decontamination tests using Fernald Incinerator Area soil originally scheduled for February 1995 was postponed to May 1995 as result of unexpected delays in the preparation of two drums of soils (∼416 kg) by FERMCO and paperwork required to arrange for export/import licenses

  8. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, January--March 1977

    Energy Technology Data Exchange (ETDEWEB)

    Card, D. H. [ed.

    1977-06-01

    A test series to evaluate the effectiveness of different emergency core coolant injection arrangements was completed. A LOFT test series was initiated to investigate the effect of break nozzle geometry on break flow and system response during a 200 percent double-ended cold leg break test. Two analyses of results of LOFT nonnuclear experiments were made. The intact loop flow resistance on LOFT system responses during loss-of-coolant experiments was evaluated. The second in a series of five tests to evaluate the effects of fuel density, initial gap width, and fill gas composition on gap conductance was performed with four BWR-type rods tested simultaneously. A test was conducted to provide steady state, power ramp, and film boiling operation behavior data on the fuel rods constructed from irradiated and unirradiated cladding and to investigate the influence of simulated fission products on cladding integrity and performance. Cladding ballooning phenomena were also investigated. Results of preliminary postirradiation examinations of irradiation effects, power-cooling mismatch, and gap conductance tests performed previously are reported. A review of FLECHT and Semiscale forced feed and gravity feed reflood heat transfer experiments was performed. A study to predict and compare surface temperature response of Semiscale electrically heated rods with LOFT nuclear rods during a Semiscale blowdown was completed. SPERT and NSRR data were analyzed to evaluate fuel failure modes and the effect of energy deposition for cold-startup conditions.

  9. The Agency's Technical Co-operation programme with Madagascar, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $3.5 million of Agency support received, Madagascar ranks 42nd among all recipients of technical assistance in the period 1958 through 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (55%), followed by expert services (32%) and training (13%). With a share of 69%, the Technical Assistance and Co-operation Fund has provided more than two-thirds of the total resources available, while 29% were made available through UNDP and 2% through assistance in kind. Extrabudgetary contributions accounted for less than one per cent. With regard to project disbursements during the past ten years, by sector, by far the largest area has been nuclear raw materials (66%), followed by nuclear physics and chemistry (18%). Only small shares have gone to nuclear safety (7%), agriculture (5%) and nuclear engineering and technology (4%)

  10. Technical assistance to Department of Energy/Office of Operational Safety Assurance Program for remedial action

    International Nuclear Information System (INIS)

    Denham, D.H.; Cross, F.T.; Kennedy, W.E. Jr.; Marks, S.; Soldat, J.K.; Stenner, R.D.

    1986-01-01

    This project was initiated in FY 1984 to provide technical assistance to the Department of Energy (DOE), Office of Operational Safety (OOS) in developing and implementing its Assurance Program for Remedial Action (APRA), i.e., overview of the DOE remedial action programs. During this second year of the project,* the technical assistance included report and procedure reviews, and assistance with conducting the Uranium Mill Tailings Remedial Action Program (UMTRAP) Office (DOE/AL) appraisal. This included participation in preappraisal visits to UMTRAP sites in Canonsburg, Pennsylvania; Grand Junction, Colorado; and Salt Lake City, Utah. Pacific Northwest Laboratory (PNL) also transferred the PNL-developed document review software to the Oak Ridge Associated Universities (ORAU) staff in Grand Junction, Colorado, in anticipation of future document reviews by the ORAU staff. Other accomplishments have included publication of two formal documents and three project reports, preparation and presentation of five topical reports at national and international meetings, two foreign trip reports, and comments on proposed draft standards of the Environmental Protection Agency (40 CFR 193). The project manager has also participated on National Council on Radiation Protection and Measurements (NCRP) and American Society for Testing and Materials (ASTM) subcommittees developing decommissioning standards, as well as International Atomic Energy Agency (IAEA) advisory groups developing environmental monitoring guidelines

  11. The Agency's Technical Co-operation programme with Sudan, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $5.7 million of Agency support received, Sudan ranks 31st among all recipients of technical assistance in the period 1958 through 1991. Over the past ten years, almost equal shares of this assistance were provided in the form of equipment (46%) and training (42%), and only a small percentage was provided in the form of expert services (12%). The best part of the resources was made available through the Technical Assistance and Co-operation Fund (77%), while in-kind and extrabudgetary contributions account for 13% and 10% of the resources, respectively. With regard to project disbursement during the past ten years, by sector, the two largest areas have been general atomic energy development (37%) and agriculture (21%), followed by nuclear medicine (14%). Smaller shares (6% each) have gone to nuclear physics and chemistry, nuclear engineering and technology, hydrology, and nuclear safety

  12. The Agency's Technical Co-operation programme with Peru, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $12.6 million of Agency support received, Peru ranks 4th among all recipients of technical assistance in the period 1958 - 1991, whereby it ranked as high as 2nd in each of the four years 1982 through 1985. More than half of the assistance during the past ten years has been provided in the form of equipment (59%), followed by expert services (29%) and training (12%). Forty-five per cent of the resources were provided by the Technical Assistance and Co-operation Fund, while 29% of the resources were made available through extrabudgetary contributions, and 21% by UNDP. The remaining 5% were provided in kind. With regard to project disbursement by sector, the largest areas have been agriculture (27%), general atomic energy development (17%), nuclear raw materials (14%), nuclear medicine (12%) and industry and hydrology (11%). Nuclear safety, nuclear engineering and technology, and nuclear physics and chemistry have each received less than ten per cent of the assistance provided

  13. The Agency's Technical Co-operation programme with Ghana, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $6.5 million of Agency support received, Ghana ranks 29th among all recipients of technical assistance in the period 1958 - 1991. More than half of the assistance during the past ten years has been provided in the form of equipment (53%), followed by training through fellowships and scientific visits (34%) and expert services (13%). Seventy-four per cent of the resources were provided by the Technical Assistance and Co-operation Fund, 13% through assistance in kind, 11% through extrabudgetary contributions, and 2% by UNDP. It should be noted that the share for extrabudgetary contributions includes an amount of $250,000 made available by the Ghanaian Government for the purchase of equipment by the Agency under a funds-in-trust arrangement. With regard to project disbursement by sector, the largest share has gone to agriculture (36%), followed by nuclear physics and chemistry (21%), nuclear medicine (16%), industry and hydrology (14%) and nuclear engineering and technology (9%)

  14. The Agency's Technical Co-operation programme with Egypt, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $22.2 million of Agency support received, Egypt ranks first among all recipients of technical assistance, not only for the period 1958 - 1991, but also held this rank in each of the five years 1982 through 1986 and in 1988. More than half of this assistance has been provided in the form of equipment (57%), followed by expert services (19%), training (17%) and sub-contracts (7%). With 42% and 43%, respectively, the Technical Assistance and Co-operation Fund and extrabudgetary contributions hold almost equal shares in the total resources available, while in-kind assistance accounts for 9% and UNDP for 6% of the resources. With regard to project disbursement during the past ten years, by sector, the two largest areas have been nuclear safety (34%) and agriculture (33%), followed by nuclear engineering and technology (11%). Smaller shares - from 4% to 7% each-- have gone to industry and hydrology, nuclear medicine, nuclear physics and chemistry, and general atomic energy development

  15. Influence of some design and operating parameters of conveyor with suspended belt and distributed drive on the technical specifications

    OpenAIRE

    Tolkachev E.N.

    2017-01-01

    The influence of several design and operating parameters of conveyor on the individual components of the stretching tension in the belt of conveyor with suspended belt and distributed drive was analyzed. The analysis of influence a number design and operating parameters on the technical specifications of conveyor with suspended belt and distributed drive was done. Recommendations on the choice of rational parameters were formulated.

  16. Technical Challenges and Opportunities of Centralizing Space Science Mission Operations (SSMO) at NASA Goddard Space Flight Center

    Science.gov (United States)

    Ido, Haisam; Burns, Rich

    2015-01-01

    The NASA Goddard Space Science Mission Operations project (SSMO) is performing a technical cost-benefit analysis for centralizing and consolidating operations of a diverse set of missions into a unified and integrated technical infrastructure. The presentation will focus on the notion of normalizing spacecraft operations processes, workflows, and tools. It will also show the processes of creating a standardized open architecture, creating common security models and implementations, interfaces, services, automations, notifications, alerts, logging, publish, subscribe and middleware capabilities. The presentation will also discuss how to leverage traditional capabilities, along with virtualization, cloud computing services, control groups and containers, and possibly Big Data concepts.

  17. The economical production of alcohol fuels from coal-derived synthesis gas. Quarterly technical progress report No. 4, July 1, 1992--September 30, 1992

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-01

    A base case flow sheet for the production of higher alcohols from coal derived synthesis gas has been completed, including an economic analysis. The details of the flow sheet and economics are in Appendix 1. The pay back period for the capital investment for the plant has been calculated as a function of the market price of the product, and this figure is also shown as Figure I in Appendix 1. The estimated installed cost is almost $500 MM, and the estimated annual operating cost is $64 MM. At a price in the vicinity of $1.00/gal for the alcohol product, the pay back period for construction of the plant is four years. These values should be considered preliminary, since many of the capital costs were obtained from other paper studies sponsored by DOE and TVA and very few values could be found from actual plants which were built. This issue is currently being addressed. The most expensive capital costs were found to be the gasifier, the cryogenic air separation plant, the steam/power generation plant and the acid gas/sulfur removal processes taken as a whole. It is planned to focus attention on alternatives to the base case. The problem is that it is less expensive to make syngas from natural gas. Therefore, it is essential to reduce the cost of syngas from coal. This is where the energy park concept becomes important. In order for this process to be economical (at current market and political conditions) a method must be found to reduce the cost of syngas manufacture either by producing energy or by-products. Energy is produced in the base case, but the amount and method has not been optimized. The economic arguments for this concept are detailed in Appendix 2.

  18. Gulf Coast Section SPE Production Operations Study Group-technical highlights from a series of frac pack treatment symposiums

    Energy Technology Data Exchange (ETDEWEB)

    McLarty, J.M.; DeBonis, V.

    1995-12-31

    One of the main functions of the SPE is to provide a means for collection, dissemination, and exchange of technical information and to provide technical forums that afford opportunities for members to maintain and upgrade their technical competence. The large chapters (such as Houston SPE) located near many oil company headquarters have the advantage of being able to bring together a cross section of service company and operator personnel representing operations and research from major and independent operators. This paper describes a series of 1-day symposiums on frac pack technology that were organized by the Houston-based Gulf Coast Section SPE Production Operations Study Group. These study sessions provided a means for the local members of the industry to further develop a new technology as a team. Publishing the major focus and contributions of the seminars will allow sharing of the technology with chapters outside of Houston.

  19. AREVA Technical Days (ATD) session 3: operations of the reactors and services division, technical and economic aspects

    International Nuclear Information System (INIS)

    2003-01-01

    These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This third session deals with the reactors technologies basics, the EPR and SWR 1000 issues and outlook, the nuclear systems of the future, the business opportunities and business models. (A.L.B.)

  20. Method for the determination of technical specifications limiting temperature in EBR-II operation

    International Nuclear Information System (INIS)

    Chang, L.K.; Hill, D.J.; Ku, J.Y.

    2004-01-01

    The methodology and analysis procedure to qualify the Mark-V and Mark-VA fuels for the Experimental Breeder Reactor II are summarized in this paper. Fuel performance data and design safety criteria are essential for thermal-hydraulic analyses and safety evaluations. Normal and off-normal operation duty cycles and transient classifications are required for the safety assessment of the fuels. Design safety criteria for steady-state normal and transient off-normal operations were developed to ensure structural integrity of the fuel pin. The maximum allowable coolant outlet temperatures and powers of subassemblies for steady-state normal operation conditions were first determined in a row-by-row basis by a thermal-hydraulic and fuel damage analysis, in which a trial-and-error approach was used to predict the maximum subassembly coolant outlet temperatures and powers that satisfy the design safety criteria for steady-state normal operation conditions. The limiting steady-state temperature and power were then used as the initial subassembly thermal conditions for the off-normal transient analysis to assess the safety performance of the fuel pin for anticipated, unlikely and extremely unlikely events. If the design safety criteria for the off-normal events are not satisfied, then the initial steady-state subassembly temperatures and/or powers are reduced and an iterative procedure is employed until the design safety criteria for off-normal conditions are satisfied, and the initial subassembly outlet coolant temperature and power are the technical specification limits for reactor operation. (author)

  1. Technical Support to an Operating PWR vis-a-vis Safety Analysis

    International Nuclear Information System (INIS)

    Gul, Subhan; Khan, M.; Chughtai, M. Kamran

    2011-01-01

    Currently a PWR of 300 MWe capacity CHASNUPP-I is in operation since the year 2000. Technical support being provided includes in-core fuel management and corresponding safety analysis for the reshuffled core for the next cycle. Currently calculation and analysis were performed for Cycle 6 to achieve the safe and economical loading pattern. The technique used is designated as out in mode (modified). In this technique, most of the fresh fuel assemblies are not directly located at the periphery of the core, but near the boundary. This technique has the advantage that without using burnable absorber we can design a low leakage core with extended cycle and maximum batch averaged burnup. (author)

  2. Computer systems in the operation, maintenance and technical support of Loviisa NPS

    International Nuclear Information System (INIS)

    Tiitinen, M.

    1993-01-01

    A description is given of how the Loviisa nuclear power plant has utilized computers in many ways in the operation, maintenance, technical support and in other functions at the plant. The evolution of the computer system can be divided into the following phases: plant commissioning (1975-80), maintenance systems development (1981-84), second generation systems take-over (1985-90) and workstation client/server systems and PC's proliferation (1991->). A short description is given of the main systems at the Loviisa plant using computers, i.e. process computer systems, the plant information system, training simulator, vibration monitoring, laboratory computer systems, PC and workstation applications. (Z.S.) 4 refs

  3. Environmental assessment for operations, upgrades, and modifications in SNL/NM Technical Area IV

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    The proposed action for this EA for Sandia National Laboratories/New Mexico Technical Area IV, includes continuing existing operations, modification of an existing accelerator (Particle Beam Fusion Accelerator II) to support defnese-related Z-pinch experiments, and construction of two transformer oil storage tanks to support the expansion of the Advanced Pulsed Power Research Module, a single pulse accelerator. Based on the analyses in the EA, DOE believes that the proposed action is not a major federal action significantly affecting the quality of the human environment within the meaning of NEPA and CEQ NEPA implementing regulations in 40 CFR 1508.18 and 1508.27. Therefore, an environmental impact statement is not required, and a Finding of No Significant Impact is issued.

  4. Staff Technical Position on geological repository operations area underground facility design: Thermal loads

    International Nuclear Information System (INIS)

    Nataraja, M.S.

    1992-12-01

    The purpose of this Staff Technical Position (STP) is to provide the US Department of Energy (DOE) with a methodology acceptable to the Nuclear Regulatory Commission staff for demonstrating compliance with 10 CFR 60.133(i). The NRC staff's position is that DOE should develop and use a defensible methodology to demonstrate the acceptability of a geologic repository operations area (GROA) underground facility design. The staff anticipates that this methodology will include evaluation and development of appropriately coupled models, to account for the thermal, mechanical, hydrological, and chemical processes that are induced by repository-generated thermal loads. With respect to 10 CFR 60.133(i), the GROA underground facility design: (1) should satisfy design goals/criteria initially selected, by considering the performance objectives; and (2) must satisfy the performance objectives 10 CFR 60.111, 60.112, and 60.113. The methodology in this STP suggests an iterative approach suitable for the underground facility design

  5. Technical Requirements Analysis and Control Systems (TRACS) Initial Operating Capability (IOC) documentation

    Science.gov (United States)

    Hammond, Dana P.

    1991-01-01

    The Technical Requirements Analysis and Control Systems (TRACS) software package is described. TRACS offers supplemental tools for the analysis, control, and interchange of project requirements. This package provides the fundamental capability to analyze and control requirements, serves a focal point for project requirements, and integrates a system that supports efficient and consistent operations. TRACS uses relational data base technology (ORACLE) in a stand alone or in a distributed environment that can be used to coordinate the activities required to support a project through its entire life cycle. TRACS uses a set of keyword and mouse driven screens (HyperCard) which imposes adherence through a controlled user interface. The user interface provides an interactive capability to interrogate the data base and to display or print project requirement information. TRACS has a limited report capability, but can be extended with PostScript conventions.

  6. Environmental assessment for operations, upgrades, and modifications in SNL/NM Technical Area IV

    International Nuclear Information System (INIS)

    1996-04-01

    The proposed action for this EA for Sandia National Laboratories/New Mexico Technical Area IV, includes continuing existing operations, modification of an existing accelerator (Particle Beam Fusion Accelerator II) to support defnese-related Z-pinch experiments, and construction of two transformer oil storage tanks to support the expansion of the Advanced Pulsed Power Research Module, a single pulse accelerator. Based on the analyses in the EA, DOE believes that the proposed action is not a major federal action significantly affecting the quality of the human environment within the meaning of NEPA and CEQ NEPA implementing regulations in 40 CFR 1508.18 and 1508.27. Therefore, an environmental impact statement is not required, and a Finding of No Significant Impact is issued

  7. 3. quarter 2006 sales revenue

    International Nuclear Information System (INIS)

    2006-10-01

    This document presents the sales revenue of the 3. quarter 2006 for the Group AREVA. The sales revenues for the first nine months of 2006 are up by 8,1% to 7,556 millions euros; the nuclear operations are up by 5,2% reflecting strong performance in the front end division; the transmission and distribution division is up by 14%. (A.L.B.)

  8. Econometric Methods within Romanian Quarterly National Accounts

    Directory of Open Access Journals (Sweden)

    Livia Marineta Drăguşin

    2013-04-01

    Full Text Available The aim of the present paper is to synthesise the main econometric methods (including the mathematical and statistical ones used in the Romanian Quarterly National Accounts compilation, irrespectively of Quarterly Gross Domestic Product (QGDP. These methods are adapted for a fast manner to operatively provide information about the country macroeconomic evolution to interested users. In this context, the mathematical and econometric methods play an important role in obtaining quarterly accounts valued in current prices and in constant prices, in seasonal adjustments and flash estimates of QGDP.

  9. Transsphenoidal surgery in patients with acromegaly: operative strategies for overcoming technically challenging anatomical variations.

    Science.gov (United States)

    Zada, Gabriel; Cavallo, Luigi M; Esposito, Felice; Fernandez-Jimenez, Julio Cesar; Tasiou, Anastasia; De Angelis, Michelangelo; Cafiero, Tullio; Cappabianca, Paolo; Laws, Edward R

    2010-10-01

    In addition to difficulties with anesthetic and medical management, transsphenoidal operations in patients with longstanding acromegaly are associated with inherent intraoperative challenges because of anatomical variations that occur frequently in these patients. The object of this study was to review the overall safety profile and anatomical/technical challenges associated with transsphenoidal surgery in patients with acromegaly. The authors performed a retrospective analysis of 169 patients who underwent endoscopic transsphenoidal operations for growth hormone-secreting adenomas to assess the incidence of surgical complications. A review of frequently occurring anatomical challenges and operative strategies employed during each phase of the operation to address these particular issues was performed. Of 169 cases reviewed, there was no perioperative mortality. Internal carotid artery injury occurred in 1 patient (0.6%) with complex sinus anatomy, who remained neurologically intact following endovascular unilateral carotid artery occlusion. Other complications included: significant postoperative epistaxis (5 patients [3%]), transient diabetes insipidus (5 patients [3%]), delayed symptomatic hyponatremia (4 patients [2%]), CSF leak (2 patients [1%]), and pancreatitis (1 patient [0.6%]). Preoperative considerations in patients with acromegaly should include a cardiopulmonary evaluation and planning regarding intubation and other aspects of the anesthetic technique. During the nasal phase of the transsphenoidal operation, primary challenges include maintaining adequate visualization and hemostasis, which is frequently compromised by redundant, edematous nasal mucosa and bony hypertrophy of the septum and the nasal turbinates. During the sphenoid phase, adequate bony removal, optimization of working space, and correlation of imaging studies to intraoperative anatomy are major priorities. The sellar phase is frequently challenged by increased sellar floor thickness

  10. Technical and economic aspects of operation of thermal and hydro power systems

    Energy Technology Data Exchange (ETDEWEB)

    Bakken, Bjoern Harald

    1997-12-31

    This thesis studies system operation and operational costs of primary and secondary control in hydro and thermal power systems. The cost of providing primary control reserves in thermal power systems is estimated to 1-3% of total production cost. Hydro power units, on the other hand, provide a very cheap primary reserve compared to thermal units. The HVDC (High Voltage Direct Current) connection can be used for primary control in either direction but the thesis only considers substitution of reserves in the thermal system with reserves from the hydro system. Since the HVDC connection is easy to control, the transient characteristics are considerably improved, and one can substitute an amount of thermal spinning reserve corresponding to the available HVDC capacity with little disturbance in any system. A more realistic alternative, at present, is to sell secondary control reserves across the HVDC connections. Keeping spinning reserve for automatic secondary control in a thermal power system is estimated to cost 3-5% of total production cost. Secondary control reserves probably cannot compete with the value of the peak load export, but one should seriously consider using part of the HVDC capacity as secondary control reserve for the thermal system during off-peak hours with. The author discusses the concept of automatic secondary control both theoretically and by simulations and finds that there are no special technical difficulties in introducing automatic secondary control in the Nordel (an organization for Nordic power cooperation) system. 78 refs., 4 figs., 23 tabs.

  11. Technical and economic aspects of operation of thermal and hydro power systems

    Energy Technology Data Exchange (ETDEWEB)

    Bakken, Bjoern Harald

    1998-12-31

    This thesis studies system operation and operational costs of primary and secondary control in hydro and thermal power systems. The cost of providing primary control reserves in thermal power systems is estimated to 1-3% of total production cost. Hydro power units, on the other hand, provide a very cheap primary reserve compared to thermal units. The HVDC (High Voltage Direct Current) connection can be used for primary control in either direction but the thesis only considers substitution of reserves in the thermal system with reserves from the hydro system. Since the HVDC connection is easy to control, the transient characteristics are considerably improved, and one can substitute an amount of thermal spinning reserve corresponding to the available HVDC capacity with little disturbance in any system. A more realistic alternative, at present, is to sell secondary control reserves across the HVDC connections. Keeping spinning reserve for automatic secondary control in a thermal power system is estimated to cost 3-5% of total production cost. Secondary control reserves probably cannot compete with the value of the peak load export, but one should seriously consider using part of the HVDC capacity as secondary control reserve for the thermal system during off-peak hours with. The author discusses the concept of automatic secondary control both theoretically and by simulations and finds that there are no special technical difficulties in introducing automatic secondary control in the Nordel (an organization for Nordic power cooperation) system. 78 refs., 4 figs., 23 tabs.

  12. Technical and economic aspects of operation of thermal and hydro power systems

    International Nuclear Information System (INIS)

    Bakken, Bjoern Harald.

    1997-01-01

    This thesis studies system operation and operational costs of primary and secondary control in hydro and thermal power systems. The cost of providing primary control reserves in thermal power systems is estimated to 1-3% of total production cost. Hydro power units, on the other hand, provide a very cheap primary reserve compared to thermal units. The HVDC (High Voltage Direct Current) connection can be used for primary control in either direction but the thesis only considers substitution of reserves in the thermal system with reserves from the hydro system. Since the HVDC connection is easy to control, the transient characteristics are considerably improved, and one can substitute an amount of thermal spinning reserve corresponding to the available HVDC capacity with little disturbance in any system. A more realistic alternative, at present, is to sell secondary control reserves across the HVDC connections. Keeping spinning reserve for automatic secondary control in a thermal power system is estimated to cost 3-5% of total production cost. Secondary control reserves probably cannot compete with the value of the peak load export, but one should seriously consider using part of the HVDC capacity as secondary control reserve for the thermal system during off-peak hours with. The author discusses the concept of automatic secondary control both theoretically and by simulations and finds that there are no special technical difficulties in introducing automatic secondary control in the Nordel (an organization for Nordic power cooperation) system. 78 refs., 4 figs., 23 tabs

  13. Elimination of quarterly urinalysis of radiation workers based on detection capability of portal monitors for internal contamination

    International Nuclear Information System (INIS)

    Ramanuja, Jayalakshmi

    2012-01-01

    Covidien is a radiopharmaceutical manufacturing company in Missouri, USA. The facility produces radionuclides for diagnostic and therapeutic use. The radionuclides of interest, 123 I, 67 Ga, 99 Mo, 99m Tc, 201 Tl, 111 In, and 131 I are fairly short lived with the exception of 51 Cr. The operating license document for the company mandated quarterly urinalysis (bioassay) of all radiation workers in the facility. This was labor intensive and did not enhance the quality of radiation protection program. Nuclear Regulatory Commission (NRC) required a technical basis to prove that there was no compromise in the radiological safety and accurate dose assessment in the event of internal contamination of radiation workers if quarterly urinalysis was discontinued. Measurements in a phantom, gamma spectroscopy analysis, as well as calculations showed that there was no need to perform quarterly urinalysis and that portal monitors and other radiological controls were sufficient to detect any chronic or acute intake of radioactivity by radiation workers. Technical evaluation showed Portal monitors can detect an Effective Dose Equivalent of 0.1 mSv (10 mrem) in a year. NRC allowed revision of operating license document and operating procedures to discontinue quarterly urinalysis. (author)

  14. Idaho National Laboratory Quarterly Occurrence Analysis - 3rd Quarter FY-2016

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-09-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 73 reportable events (23 from the 3rd Qtr FY-16 and 50 from the prior three reporting quarters), as well as 45 other issue reports (including events found to be not reportable and Significant Category A and B conditions) identified at INL during the past 12 months (16 from this quarter and 29 from the prior three quarters).

  15. Idaho National Laboratory Quarterly Occurrence Analysis - 1st Quarter FY 2016

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-03-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 74 reportable events (16 from the 1st Qtr FY-16 and 58 from the prior three reporting quarters), as well as 35 other issue reports (including events found to be not reportable and Significant Category A and B conditions) identified at INL during the past 12 months (15 from this quarter and 20 from the prior three quarters).

  16. Emergency notification and assistance technical operations manual. Emergency preparedness and response. Date effective: 1 February 2007

    International Nuclear Information System (INIS)

    2007-01-01

    The Convention on Early Notification of a Nuclear Accident (the 'Early Notification Convention') and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (the 'Assistance Convention') are the prime legal instruments that establish an international framework to facilitate the exchange of information and the prompt provision of assistance in the event of a nuclear or radiological emergency, with the aim of minimizing the consequences. The International Atomic Energy Agency has specific functions assigned to it under these Conventions, to which, in addition to a large number of States, the World Health Organization (WHO), the World Meteorological Organization (WMO) and the Food and Agriculture Organization of the United Nations (FAO) are full parties. The arrangements provided between the IAEA, States that are IAEA Member States and/or Parties to one or both Conventions, all other relevant international intergovernmental organizations, and other States for facilitating the implementation of these Conventions - specifically concerning those articles that are operational in nature - are documented in the Emergency Notification and Assistance Technical Operations Manual (ENATOM). ENATOM was first issued on 18 January 1989. Member States, Parties to the Early Notification and Assistance Conventions, relevant international organizations and other States have since then regularly received updates to the manual. In 2000, a complete revision of ENATOM was reissued as EPR-ENATOM (2000) to reflect technological developments, changes in operational concepts, views on standards in the area of emergency preparedness and response, and Member States' expectations. Since then ENATOM has been reviewed and reissued biennially in line with the review cycle of the Joint Radiation Emergency Management Plan of the International Organizations (the 'Joint Plan'). Since the last edition of ENATOM in 2004, several factors have warranted some modifications to

  17. The Agency's Technical Co-operation programme with Argentina, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $7.5 million of Agency support received, Argentina ranks 22nd among all recipients of technical assistance during the period 1958 through 1991. Forty-six per cent of the assistance received during the past ten years has been provided in the form of equipment, complemented by expert services (40%) and training (14%). The largest share of the resources was made available by UNDP (87%), and only small shares were provided through the TACF (12%) and assistance in kind (less than 1%). With regard to total disbursements - by sector - under those projects that were operational during the period 1982 through mid-December 1992, by far the largest area has been nuclear engineering and technology (91%), while only very small shares went to nuclear safety (4%), industry and hydrology (3%) and agriculture (2%). During the same period, the country has provided experts and training course lectures for a total of 601 assignments, and has hosted 153 fellowships and scientific visits as well as 42 regional and interregional training courses with a total of 568 participants

  18. TECHNICAL AND ECONOMIC EVALUATION OF THE HARVEST OF EUCALYPTUS WITH FELLER-BUNCHER IN DIFFERENT OPERATING CONDITIONS

    Directory of Open Access Journals (Sweden)

    Danilo Simões

    2010-12-01

    Full Text Available This study aimed to technically and economically evaluate the Feller-buncher in different conditions of harvest in eucalyptus forests of second cut. The technical analysis included a study of time and movements by the method of continuous time, and operational performance was determined by volume in cubic meters of harvested wood. The economic analysis included the parameters of operational cost, harvest cost and energy consumption. The analysis of the data showed that the composition of main line harvesting and the arrangement of bundles of trees influenced operational performance. The average operational cost was US$ 86.26 per hour of actual work, which resulted in an average cost of forest harvesting of US$ 1.09 m-³.

  19. Quarterly Financial Report

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

    acray

    2011-06-30

    Jun 30, 2011 ... 2 IDRC QUARTERLY FINANCIAL REPORT JUNE 2011. Consolidated .... spending on capacity-building projects as well as to management's decision to restrict capacity- building ...... The investments in financial institutions.

  20. Influence of some design and operating parameters of conveyor with suspended belt and distributed drive on the technical specifications

    Directory of Open Access Journals (Sweden)

    Tolkachev E.N.

    2017-03-01

    Full Text Available The influence of several design and operating parameters of conveyor on the individual components of the stretching tension in the belt of conveyor with suspended belt and distributed drive was analyzed. The analysis of influence a number design and operating parameters on the technical specifications of conveyor with suspended belt and distributed drive was done. Recommendations on the choice of rational parameters were formulated.

  1. 78 FR 43091 - Technical Operations Safety Action Program (T-SAP) and Air Traffic Safety Action Program (ATSAP)

    Science.gov (United States)

    2013-07-19

    ... Administration 14 CFR Part 193 [Docket No.: FAA-2013-0375] Technical Operations Safety Action Program (T-SAP) and... Disclosure. SUMMARY: The FAA is proposing that safety information provided to it under the T-SAP, established... to the FAA under the T-SAP and ATSAP, so the FAA can learn about and address aviation safety hazards...

  2. Report on the consultants` meeting on technical aspects of the co-operation of nuclear reaction data centers

    Energy Technology Data Exchange (ETDEWEB)

    Lemmel, H D; Schwerer, O; Wienke, H [eds.

    1995-10-01

    The IAEA Nuclear Data Section convenes in annual intervals coordination meetings of the Network of the Nuclear Reaction Data Center. The present meeting dealt with technical matters of the nuclear data compilation and exchange by means of the jointly operated computerized systems CINDA, EXFOR, ENDF and others. Refs, figs and tabs.

  3. Report on the consultants' meeting on technical aspects of the co-operation of nuclear reaction data centers

    International Nuclear Information System (INIS)

    Lemmel, H.D.; Schwerer, O.; Wienke, H.

    1995-10-01

    The IAEA Nuclear Data Section convenes in annual intervals coordination meetings of the Network of the Nuclear Reaction Data Center. The present meeting dealt with technical matters of the nuclear data compilation and exchange by means of the jointly operated computerized systems CINDA, EXFOR, ENDF and others. Refs, figs and tabs

  4. Technical requirements for implementation of an individual monitoring service for evaluation of operational quantity HP(10) using thermoluminescent dosimetry

    International Nuclear Information System (INIS)

    Francisco, Adelaide Benedita Armando

    2016-01-01

    This work aims to establish technical requirements for the development of a TLDs system for the assessment of operational quantity H P (10), in order to implement an external individual monitoring service in countries who do not have. This allows a better understanding of the technic and the thermoluminescent dosimetry system, thus contributing to identify the technical criteria to be followed by a dosimetry laboratory and evaluation of the dosimetric system performance. For this, the review of the specific literature of the dosimetry field was conducted and later the type and performance tests that must be followed by a dosimetric system were reproduced in practice. In additional was made a analysis of internationals standards norms and the technical regulation used in Brazil, to define the essentials type testes to a dosimetric system. To check the performance of a dosimetry system, a performance analysis of the Brazilian TLDs system was carried out over the past 6 years using the trumpet curve, where it was observed that most of TLDs system, in this review period, were approved and have excellent performance. The technical requirements for the development of a thermoluminescent dosimetry system ensure that the system provides technically reliable results and allow demonstration of compliance with the standard criteria established by national and international standards, and the implementation of the dosimetry system, is verified the compliance of the annual doses limits set for occupationally exposed. (author)

  5. Emergency notification and assistance technical operations manual. Emergency preparedness and response. Date effective: 1 December 2000

    International Nuclear Information System (INIS)

    2000-11-01

    The Convention on Early Notification of a Nuclear Accident (the 'Early Notification Convention') and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (the 'Assistance Convention') are the prime legal instruments that establish an international framework to facilitate the exchange of information and the prompt provision of assistance in the event of a nuclear accident or radiological emergency, with the aim of minimizing the consequences. The International Atomic Energy Agency (IAEA) has specific functions assigned to it under these Conventions, to which the World Health Organization (WHO), the World Meteorological Organization (WMO) and the Food and Agriculture Organization of the United Nations (FAO) are full parties. Since 1989, the arrangements between the IAEA, States which are IAEA Member States and/or Parties to one or both Conventions, all other relevant international intergovernmental organizations, and other States for facilitating the implementation of the Conventions - specifically of those of their articles which are operational in nature have been documented in the Emergency Notification and Assistance Technical Operations Manual (ENATOM). Recent events, for example, the launch of the Cassini satellite (USA, 1997), the Acerinox accident (Spain, 1998), the JCO criticality accident (Japan, 1999), the Istanbul accident (Turkey, 1999) and the Samut Prakarn accident (Thailand, 2000), have raised new issues and highlighted the expectation of States that the IAEA will use the framework of the Early Notification and Assistance Conventions to obtain and provide real-time emergency related information on such events. While the Early Notification Convention requires States Parties to report only accidents that may have significant transboundary radiological consequences, States may under the Assistance Convention legitimately request the assistance of the IAEA or an Accident State in obtaining information concerning a

  6. Technical and operational feasibility of psychrophilic anaerobic digestion biotechnology for processing ammonia-rich waste

    International Nuclear Information System (INIS)

    Massé, Daniel I.; Rajagopal, Rajinikanth; Singh, Gursharan

    2014-01-01

    Highlights: • Long-term anaerobic digestion (AD) process at high-ammonia (>5 gN/L) is limited. • PADSBR technology was validated to treat N-rich waste with 8.2 ± 0.3 gNH 3 -N/L. • Excess ammonia (8.2 gN/L) did not affect the digestion process with no inhibition. • VFA, an indicator for process stability, did not accumulate in PADSBR. • Biomass acclimation in PADSBR ensured a high-stabilization of the AD process. - Abstract: Ammonia nitrogen plays a critical role in the performance and stability of anaerobic digestion (AD) of ammonia rich wastes like animal manure. Nevertheless, inhibition due to high ammonia remains an acute limitation in AD process. A successful long-term operation of AD process at high ammonia (>5 gN/L) is limited. This study focused on validating technical feasibility of psychrophilic AD in sequencing batch reactor (PADSBR) to treat swine manure spiked with NH 4 Cl up to 8.2 ± 0.3 gN/L, as a representative of N-rich waste. CODt, CODs, VS removals of 86 ± 3, 82 ± 2 and 73 ± 3% were attained at an OLR of 3 gCOD/L.d, respectively. High-ammonia had no effect on methane yields (0.23 ± 0.04 L CH 4 /gTCOD fed ) and comparable to that of control reactors, which fed with raw swine manure alone (5.5 gN/L). Longer solids/hydraulic retention times in PADSBRs enhanced biomass acclimation even at high-ammonia. Thus VFA, an indicator for process stability, did not accumulate in PADSBR. Further investigation is essential to establish the maximum concentrations of TKN and free ammonia that the PADSBR can sustain

  7. Quarterly oil statistics. First quarter 1978

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-01

    The aim of this report is to provide rapid, accurate and detailed statistics on oil supply and demand in the OECD area. Main components of the system are: complete balances of production, trade, refinery intake and output, final consumption, stock levels and changes; separate data for crude oil, NGL, feedstocks and nine product groups; separate trade data for main product groups, LPG and naphtha; imports for 41 origins; exports for 29 destinations; marine bunkers and deliveries to international civil aviation by product group; aggregates of quarterly data to annual totals; and natural gas supply and consumption.

  8. Surgeons' and trainees' perceived self-efficacy in operating theatre non-technical skills.

    Science.gov (United States)

    Pena, G; Altree, M; Field, J; Thomas, M J W; Hewett, P; Babidge, W; Maddern, G J

    2015-05-01

    An important factor that may influence an individual's performance is self-efficacy, a personal judgement of capability to perform a particular task successfully. This prospective study explored newly qualified surgeons' and surgical trainees' self-efficacy in non-technical skills compared with their non-technical skills performance in simulated scenarios. Participants undertook surgical scenarios challenging non-technical skills in two simulation sessions 6 weeks apart. Some participants attended a non-technical skills workshop between sessions. Participants completed pretraining and post-training surveys about their perceived self-efficacy in non-technical skills, which were analysed and compared with their performance in surgical scenarios in two simulation sessions. Change in performance between sessions was compared with any change in participants' perceived self-efficacy. There were 40 participants in all, 17 of whom attended the non-technical skills workshop. There was no significant difference in participants' self-efficacy regarding non-technical skills from the pretraining to the post-training survey. However, there was a tendency for participants with the highest reported self-efficacy to adjust their score downwards after training and for participants with the lowest self-efficacy to adjust their score upwards. Although there was significant improvement in non-technical skills performance from the first to second simulation sessions, a correlation between participants' self-efficacy and performance in scenarios in any of the comparisons was not found. The results suggest that new surgeons and surgical trainees have poor insight into their non-technical skills. Although it was not possible to correlate participants' self-belief in their abilities directly with their performance in a simulation, in general they became more critical in appraisal of their abilities as a result of the intervention. © 2015 BJS Society Ltd Published by John Wiley & Sons Ltd.

  9. Technical Review of Operator's Destructive Analyses at the Rokkasho Reprocessing Plant: Strengthening the Transparency of the Operator's Measurement System

    International Nuclear Information System (INIS)

    Sato, N.; Katchi, T.; Niitsu, Y.; Duhamel, G.; Decaillon, J.-G.; Toervenyi, A.; Sayama, H.; Hara, S.

    2015-01-01

    The Rokkasho Reprocessing Plant is a large-scale nuclear facility in Japan. For the purposes of process control, product management and nuclear material accountancy for safeguards purposes, the laboratory of the facility operator analyzes thousands of samples from various process streams and with a multitude of matrices. Transparency of operational procedures, quality control measures and sample analytical results among the facility operator and state and international safeguards authorities are required to assess the facility operator's measurement system, and thus to assure a credible safeguards approach. The facility operator, Japan Nuclear Fuel, Limited (JNFL), is engaged in continuous improvement of its nuclear material analyzes. For the declarations to the inspectorates, it is important that JNFL and the safeguards authorities be able to confirm that the analytical methods used by JNFL are reliable and meet the latest version of the International Target Values. Since 2012 JNFL, the IAEA and the SSAC have carried out several technical reviews of the destructive analysis (DA) processes as a means of strengthening the transparency of the DA measurement systems. The goal of the DA technical reviews is to (1) assess past commitments of the JNFL plan for analytical improvement, (2) review the JNFL Quality System by means of documentation reviews and in-field demonstrations, and (3) review the analytical performance of the JNFL lab through its own results or from inter-laboratory comparison exercises. Throughout this process, subject-matter experts from all organizations met with JNFL laboratory staff and discussed analytical concerns and solutions. The outcome of these technical reviews was a series of recommendations to JNFL for strengthening its plan for continuous improvement. This paper presents the methodology of the DA technical reviews, the communication scheme and some examples of the outcome for JNFL to improve its DA methods and analytical

  10. Applied Meteorology Unit (AMU) Quarterly Report - Fourth Quarter FY-10

    Science.gov (United States)

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

    2010-01-01

    Three AMU tasks were completed in this Quarter, each resulting in a forecast tool now being used in operations and a final report documenting how the work was done. AMU personnel completed the following tasks (1) Phase II of the Peak Wind Tool for General Forecasting task by delivering an improved wind forecasting tool to operations and providing training on its use; (2) a graphical user interface (GUI) she updated with new scripts to complete the ADAS Update and Maintainability task, and delivered the scripts to the Spaceflight Meteorology Group on Johnson Space Center, Texas and National Weather Service in Melbourne, Fla.; and (3) the Verify MesoNAM Performance task after we created and delivered a GUI that forecasters will use to determine the performance of the operational MesoNAM weather model forecast.

  11. Emergency notification and assistance technical operations manual. Emergency preparedness and response. Date effective: 1 December 2002

    International Nuclear Information System (INIS)

    2002-11-01

    The Convention on Early Notification of a Nuclear Accident (the 'Early Notification Convention') and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (the 'Assistance Convention') are the prime legal instruments that establish an international framework to facilitate the exchange of information and the prompt provision of assistance in the event of a nuclear accident or radiological emergency, with the aim of minimizing their consequences. The International Atomic Energy Agency (IAEA) has specific functions assigned to it under these Conventions, to which, in addition to a large number of States (Section 1.7), the World Health Organization (WHO), the World Meteorological Organization (WMO) and the Food and Agriculture Organization of the United Nations (FAO) are full parties. The arrangements between the IAEA, States that are IAEA Member States and/or Parties to one or both Conventions, all other relevant international intergovernmental organizations, and other States for facilitating the implementation of these Conventions specifically concerning those articles that are operational in nature - are documented in the Emergency Notification and Assistance Technical Operations Manual (ENATOM). In 2000, a complete revision of ENATOM, with all relevant sections updated, withdrawn or replaced with new material, was reissued as EPR-ENATOM (2000) to reflect new technological developments, operational concepts, views on standards in the area of emergency preparedness and response, and Member States' expectations. A separate publication, EPR-JPLAN (2000), the Joint Radiation Emergency Management Plan of the International Organizations (Joint Plan'), described a common understanding of how each of six co-sponsoring international organizations will act during a response and in making preparedness arrangements. It is intended that the ENATOM is reviewed and reissued biennially in line with the review cycle of the Joint Plan. Since the

  12. The exploitation of the Saturne synchrotron during the forth quarter of 1960; L'exploitation du synchrotron Saturne pendant le 4eme trimestre 1960

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1961-01-15

    This document reports information and data regarding the operation of the Saturne synchrotron during the fourth quarter of 1960. It addresses the machine operation (acceleration cycles, beam intensity, technical incidents, time table), hardware studies (corrector circuit under high fields, intensity increase), physics experiments (on counters, in bubble chambers, target irradiation), measures and measurements regarding the protection against radiations (comparison of irradiation levels in different areas of the synchrotron, annual evolution), the liquefactor activity (nitrogen and hydrogen consumption and production data)

  13. The exploitation of the Saturne synchrotron during the first quarter of 1959; L'exploitation du synchrotron Saturne pendant le 1er trimestre 1959

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-05-15

    After having recalled some important events which occurred in 1958 regarding the operation of the Saturne synchrotron, this document first reports facts concerning the operation of the synchrotron (technical incidents are mentioned), experiments performed on the equipment (trajectory anomalies), physics experiments (use of fixed targets and of a target with radial projection, experiments in a bubble chamber), measures and measurements regarding protection against radiations during the first quarter of 1959.

  14. Toward feasible, valid, and reliable video-based assessments of technical surgical skills in the operating room

    DEFF Research Database (Denmark)

    Aggarwal, R.; Grantcharov, T.; Moorthy, K.

    2008-01-01

    .72). Conclusions: Video-based technical skills evaluation in the operating room is feasible, valid and reliable. Global rating scales hold promise for summative assessment, though further work is necessary to elucidate the value of procedural rating scales Udgivelsesdato: 2008/2......Objective: To determine the feasibility, validity, inter-rater, and intertest reliability of 4 previously published video-based rating scales, for technical skills assessment on a benchmark laparoscopic procedure. Summary Background Data: Assessment of technical skills is crucial...... to the demonstration and maintenance of competent healthcare practitioners. Traditional assessment methods are prone to subjectivity through a lack of proven validity and reliability. Methods: Nineteen surgeons (6 novice and 13 experienced) performed a median of 2 laparoscopic cholecystectomies each (range 1-5) on 53...

  15. Methods of monitoring the technical condition of the braking system of an autonomous vehicle during operation

    Science.gov (United States)

    Revin, A.; Dygalo, V.; Boyko, G.; Lyaschenko, M.; Dygalo, L.

    2018-02-01

    Possibilities of diagnosing of a technical condition of braking system of the autonomous vehicles with automated modules while in service are considered. The concept of sharing of onboard means and stands for diagnosing is presented.

  16. Prototype design for a predictive model to improve evacuation operations : technical report.

    Science.gov (United States)

    2011-08-01

    Mass evacuations of the Texas Gulf Coast remain a difficult challenge. These events are massive in scale, : highly complex, and entail an intricate, ever-changing conglomeration of technical and jurisdictional issues. : This project focused primarily...

  17. Analysis of the prevailing standard and technical documents for their applicability under conditions of the 'Ukrytie' operation and technical proposals relating to the elaboration of new ones concerning fire safety

    International Nuclear Information System (INIS)

    Nazarenko, B.S.; Emets, V.G.

    1998-01-01

    An analysis of the prevailing laws and standards and technical documents (STD) to ensure safe operation of nuclear power installations, with requirements of nuclear, radiation and fire safety taken into account, has been performed. Proposals on application of some items of prevailing STD under conditions of the 'Ukrytie' operation are presented. Also given are technical proposals on correction of the prevailing operational standard documents and elaboration of special STD

  18. Idaho National Laboratory Quarterly Performance Analysis - 3rd Quarter FY2014

    Energy Technology Data Exchange (ETDEWEB)

    Lisbeth A. Mitchell

    2014-09-01

    This report is published quarterly by the Idaho National Laboratory (INL) Performance Assurance Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of occurrence reports and other non-reportable issues identified at INL from July 2013 through June 2014.

  19. Idaho National Laboratory Quarterly Performance Analysis for the 2nd Quarter FY 2015

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth A. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-04-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of events for the 2nd Qtr FY-15.

  20. Idaho National Laboratory Quarterly Performance Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-11-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 60 reportable events (23 from the 4th Qtr FY14 and 37 from the prior three reporting quarters) as well as 58 other issue reports (including not reportable events and Significant Category A and B conditions) identified at INL from July 2013 through October 2014. Battelle Energy Alliance (BEA) operates the INL under contract DE AC07 051D14517.

  1. ER Consolidated Quarterly Report October 2014

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-10-01

    This Environmental Restoration Operations (ER) Consolidated Quarterly Report (ER Quarterly Report) provides the status of ongoing corrective actions and related Long- Term Stewardship (LTS) activities being implemented by Sandia National Laboratories, New Mexico (SNL/NM) ER for the April, May, and June 2014 quarterly reporting period. Section 2.0 provides the status of ER Operations activities including closure activities for the Mixed Waste Landfill (MWL), project management and site closure, and hydrogeologic characterizations. Section 3.0 provides the status of LTS activities that relate to the Chemical Waste Landfill (CWL) and the associated Corrective Action Management Unit (CAMU). Section 4.0 provides the references noted in Section I of this report.

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

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, John R.; Cochran, John R.

    2017-04-01

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

  3. AlpArray - technical strategies for large-scale European co-operation in broadband seismology

    Science.gov (United States)

    Brisbourne, A.; Clinton, J.; Hetenyi, G.; Pequegnat, C.; Wilde-Piorko, M.; Villasenor, A.; Comelli, P.; AlpArray Working Group

    2012-04-01

    AlpArray is a new initiative to study the greater Alpine area with a large-scale broadband seismological network. The interested parties (currently 32 institutes in 12 countries) plan to combine their existing infrastructures into an all-out transnational effort that includes data acquisition, processing, imaging and interpretation. The experiment will encompass the greater Alpine area, from the Black Forest in the north to the Northern Apennines in the south and from the Pannonian Basin in the east to the French Massif Central in the west. We aim to cover this region with high-quality broadband seismometers by combining the ~400 existing permanent stations with an additional 400+ instruments from mobile pools. In this way, we plan to achieve homogeneous and high resolution coverage while also deploying densely spaced stations along swaths across key parts of the Alpine chain. These efforts on land will be combined with deployments of ocean bottom seismometers in the Mediterranean Sea. Significant progress has already been made in outlining the scientific goals and funding strategy. A brief overview of these aspects of the initiative will be presented here. However, we will concentrate on the technical aspects: How efficient large-scale integration of existing infrastructures can be achieved. Existing permanent station coverage within the greater Alpine area has been collated and assessed for data availability, allowing strategies to be developed for network densification to ensure a robust backbone network: An anticipated deployment strategy has been drawn up to optimise array coverage and data quality. The augmented backbone network will be supplemented by more densely spaced temporary arrays targeting more specific scientific questions. For these temporary arrays, a strategy document has been produced to outline standards for station installation, data acquisition, processing, archival and dissemination. All these operations are of course vital. However, data

  4. Platform development for merging various information sources for water management: methodological, technical and operational aspects

    Science.gov (United States)

    Galvao, Diogo

    2013-04-01

    As a result of various economic, social and environmental factors, we can all experience the increase in importance of water resources at a global scale. As a consequence, we can also notice the increasing need of methods and systems capable of efficiently managing and combining the rich and heterogeneous data available that concerns, directly or indirectly, these water resources, such as in-situ monitoring station data, Earth Observation images and measurements, Meteorological modeling forecasts and Hydrological modeling. Under the scope of the MyWater project, we developed a water management system capable of satisfying just such needs, under a flexible platform capable of accommodating future challenges, not only in terms of sources of data but also on applicable models to extract information from it. From a methodological point of view, the MyWater platform obtains data from distinct sources, and in distinct formats, be they Satellite images or meteorological model forecasts, transforms and combines them in ways that allow them to be fed to a variety of hydrological models (such as MOHID Land, SIMGRO, etc…), which themselves can also be combined, using such approaches as those advocated by the OpenMI standard, to extract information in an automated and time efficient manner. Such an approach brings its own deal of challenges, and further research was developed under this project on the best ways to combine such data and on novel approaches to hydrological modeling (like the PriceXD model). From a technical point of view, the MyWater platform is structured according to a classical SOA architecture, with a flexible object oriented modular backend service responsible for all the model process management and data treatment, while the information extracted can be interacted with using a variety of frontends, from a web portal, including also a desktop client, down to mobile phone and tablet applications. From an operational point of view, a user can not only see

  5. Demonstration of Selective Catalytic Reduction (SCR) technology for the control of nitrogen oxide (NO{sub x}) emissions from high-sulfur coal-fired boilers. Technical progress report, first and second quarters 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    The objective of this project is to demonstrate and evaluate commercially available Selective Catalytic Reduction (SCR) catalysts from U.S., Japanese and European catalyst suppliers on a high-sulfur U.S. coal-fired boiler. SCR is a post-combustion nitrogen oxide (NO{sub x}) control technology that involve injecting ammonia into the flue gas generated from coal combustion in a boiler. The flue gas containing ammonia is then passed through a reactor that contains a specialized catalyst. In the presence of the catalyst, the ammonia reacts with NO{sub x} to form nitrogen and water vapor. Although SCR is widely practiced in Japan and Europe on gas-, oil-, and low-sulfur coal-fired boilers, there are several technical uncertainties associated with applying SCR to U.S. coals. These uncertainties include: (1) potential catalyst deactivation due to poisoning by trace metal species present in U.S. coals that are not present in other fuels; (2) performance of the technology and effects on the balance-of-plant equipment in the presence of high amounts of SO{sub 2} and SO{sub 3}; and (3) performance of a wide variety of SCR catalyst compositions, geometries and methods of manufacture under typical high-sulfur coal-fired utility operating conditions. These uncertainties are being explored by operating a series of small-scale SCR reactors and simultaneously exposing different SCR catalysts to flue gas derived from the combustion of high sulfur U.S. coal. The project is being conducted in the following three phases: permitting, environmental monitoring plan and preliminary engineering; detailed design engineering and construction; and operation, testing, disposition and final report. The project was in the operation and testing phase during this reporting period. Accomplishments for this period are described.

  6. AREVA Technical Days (ATD) session 4: operations of the front-end division of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    2004-01-01

    These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This fourth session deals with the strategic and financial significance of the Areva mining operations, the Areva chemistry business, the Areva enrichment business and the Areva fuel business. (A.L.B.)

  7. Improved Management of the Technical Interfaces Between the Hanford Tank Farm Operator and the Hanford Waste Treatment Plant - 13383

    Energy Technology Data Exchange (ETDEWEB)

    Duncan, Garth M. [Bechtel National Inc., 2435 Stevens Center Place, Richland, Washington, 99352 (United States); Saunders, Scott A. [Washington River Protection Solutions, P.O. Box 850, Richland, Washington, 99352 (United States)

    2013-07-01

    The Department of Energy (DOE) is constructing the Waste Treatment and Immobilization Plant (WTP) at the Hanford site in Washington to treat and immobilize approximately 114 million gallons of high level radioactive waste (after all retrievals are accomplished). In order for the WTP to be designed and operated successfully, close coordination between the WTP engineering, procurement, and construction contractor, Bechtel National, Inc. and the tank farms operating contractor (TOC), Washington River Protection Solutions, LLC, is necessary. To develop optimal solutions for DOE and for the treatment of the waste, it is important to deal with the fact that two different prime contractors, with somewhat differing contracts, are tasked with retrieving and delivering the waste and for treating and immobilizing that waste. The WTP and the TOC have over the years cooperated to manage the technical interface. To manage what is becoming a much more complicated interface as the WTP design progresses and new technical issues have been identified, an organizational change was made by WTP and TOC in November of 2011. This organizational change created a co-located integrated project team (IPT) to deal with mutual and interface issues. The Technical Organization within the One System IPT includes employees from both TOC and WTP. This team has worked on a variety of technical issues of mutual interest and concern. Technical issues currently being addressed include: - The waste acceptance criteria; - Waste feed delivery and the associated data quality objectives (DQO); - Evaluation of the effects of performing a riser cut on a single shell tank on WTP operations; - The disposition of secondary waste from both TOC and WTP; - The close coordination of the TOC double shell tank mixing and sampling program and the Large Scale Integrated Test (LSIT) program for pulse jet mixers at WTP along with the associated responses to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation

  8. Improved Management of the Technical Interfaces Between the Hanford Tank Farm Operator and the Hanford Waste Treatment Plant - 13383

    International Nuclear Information System (INIS)

    Duncan, Garth M.; Saunders, Scott A.

    2013-01-01

    The Department of Energy (DOE) is constructing the Waste Treatment and Immobilization Plant (WTP) at the Hanford site in Washington to treat and immobilize approximately 114 million gallons of high level radioactive waste (after all retrievals are accomplished). In order for the WTP to be designed and operated successfully, close coordination between the WTP engineering, procurement, and construction contractor, Bechtel National, Inc. and the tank farms operating contractor (TOC), Washington River Protection Solutions, LLC, is necessary. To develop optimal solutions for DOE and for the treatment of the waste, it is important to deal with the fact that two different prime contractors, with somewhat differing contracts, are tasked with retrieving and delivering the waste and for treating and immobilizing that waste. The WTP and the TOC have over the years cooperated to manage the technical interface. To manage what is becoming a much more complicated interface as the WTP design progresses and new technical issues have been identified, an organizational change was made by WTP and TOC in November of 2011. This organizational change created a co-located integrated project team (IPT) to deal with mutual and interface issues. The Technical Organization within the One System IPT includes employees from both TOC and WTP. This team has worked on a variety of technical issues of mutual interest and concern. Technical issues currently being addressed include: - The waste acceptance criteria; - Waste feed delivery and the associated data quality objectives (DQO); - Evaluation of the effects of performing a riser cut on a single shell tank on WTP operations; - The disposition of secondary waste from both TOC and WTP; - The close coordination of the TOC double shell tank mixing and sampling program and the Large Scale Integrated Test (LSIT) program for pulse jet mixers at WTP along with the associated responses to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation

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

    Energy Technology Data Exchange (ETDEWEB)

    Showalter, Mary Ann

    2008-09-16

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Showalter, Mary Ann

    2008-01-28

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-02-02

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

  12. A QUARTER CENTURY OF NUCLEAR WASTE MANAGEMENT IN JAPAN

    International Nuclear Information System (INIS)

    Masuda, S.

    2002-01-01

    This paper is entitled ''A QUARTER CENTURY OF NUCLEAR WASTE MANAGEMENT IN JAPAN''. Since the first statement on the strategy for radioactive waste management in Japan was made by the Atomic Energy Commission (AEC) in 1976, a quarter century has passed, in which much experience has been accumulated both in technical and social domains. This paper looks back in this 25-year history of radioactive waste management in Japan by highlighting activities related to high-level radioactive waste (HLW) disposal

  13. Coal demonstration plants. Quarterly report, July--September 1977

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-02-01

    The objective of DOE's demonstration plant program is to establish the technical and financial feasibility of coal conversion technologies proven during pilot plant testing. Demonstration plants will minimize the technical and economic risks of commercialization by providing a near commercial size plant for testing and production. Thus, DOE is sponsoring the development of a series of demonstration plants, each of which will be a smaller version of commercial plants envisioned for the 1980's. These plants will be wholly integrated, self-sufficient in terms of heat generation, and dependent only on feedstock of coal, water, and air. Contracts for designing, constructing, and operating the demonstration plants will be awarded through competitive procedures and will be jointly funded. The conceptual design phase will be funded by the government, with the detailed design, procurement, construction, and operation phases being co-funded, 50% from industry and 50% from the government. The cost involved in building and operating a demonstration plant will probably be between $200 million and $500 million, depending on the size of the plant. Twenty-two projects involving demonstration plants or support projects for such plants are reviewed, including a summary for each of progress in the quarter. (LTN)

  14. Coal demonstration plants. Quarterly report, April--June 1977

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-01-01

    The objective of DOE's demonstration plant program is to establish the technical and financial feasibility of coal conversion technologies proven during pilot plant testing. Demonstration plants will minimize the technical and economic risks of commercialization by providing a near commercial size plant for testing and production. Thus, DOE is sponsoring the development of a series of demonstration plants, each of which will be a smaller version of commercial plants envisioned for the 1980's. These plants will be wholly integrated, self-sufficient in terms of heat generation, and dependent only on feedstock of coal, water, and air. Under the DOE program, contracts for designing, constructing, and operating the demonstration plants will be awarded through competitive procedures and will be jointly funded. The conceptual design phase will be funded by the government, with the detailed design, procurement, construction, and operation phases being co-funded, 50% from industry and 50% from the government. The cost involved in building and operating a demonstration plant will probably be between $200 million and $500 million, depending on the size of the plant. Six of these demonstration plant projects are described and progress in the quarter is summarized. Several support and complementary projects are described (fuel feeding system development, performance testing and comparative evaluation, engineering support, coal grinding equipment development and a critical components test facility). (LTN)

  15. South African Crime Quarterly

    African Journals Online (AJOL)

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

  16. English Leadership Quarterly, 1993.

    Science.gov (United States)

    Strickland, James, Ed.

    1993-01-01

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

  17. Quarterly fiscal policy

    NARCIS (Netherlands)

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

    2014-01-01

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

  18. Non-governmental organizational health operations in humanitarian crises: the case for technical support units.

    Science.gov (United States)

    Greenough, P Gregg; Nazerali, Rahim; Fink, Sheri; VanRooyen, Michael J

    2007-01-01

    As the humanitarian health response industry grows, there is a need for technical health expertise that can build an evidence base around outcome measures and raise the quality and accountability of the health relief response. We propose the formation of technical support units (TSUs), entities of health expertise institutionalized within humanitarian non-governmental organizations (NGOs), which will bridge the gap between the demand for evidence-based, humanitarian programming and the field capacity to accomplish it. With the input of major humanitarian NGOs and donors, this paper discusses the attributes and capacities ofTSUs; and the mechanisms for creating and enhancing TSUs within the NGO management structure.

  19. Risk based optimization of technical specifications for operation of nuclear power plants

    International Nuclear Information System (INIS)

    1993-12-01

    The objective of the report is to present an overview of the risk and reliability based approaches (using a probabilistic safety assessment (PSA)) for improving nuclear power plant technical specifications (TS). In that case, it will provide an information base to the Member States in seeking PSA based applications to enhance the effectiveness of their technical specifications. To achieve this objective, the report discusses the basic objectives and reasons for seeking TS changes, the methods, data requirements and uses of different types of applications, and an overview of different applications that have been completed, including detailed descriptions of selected applications. Refs, figs and tabs

  20. The Agency's technical co-operation programme with Syrian Arab Republic 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in Syrian Arab Republic carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  1. The Agency's technical co-operation programme with Cote d'Ivoire 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in Cote d'Ivoire carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  2. The Agency's technical co-operation programme with the People's Republic of China 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in the People's Republic of China carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  3. The Agency's technical co-operation programme with the Republic of Korea 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in the Republic of Korea carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  4. The Agency's technical co-operation programme with the Islamic Republic of Iran 1985-1995 country programme summaries

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains a review of the Agency's technical co-operation activities in the Islamic Republic of Iran carried out during 1985-1995. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  5. The Agency's technical co-operation programme with the Islamic Republic of Iran 1983-1993 country programme summaries

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains a review of the Agency's technical co-operation activities in the Islamic Republic of Iran carried out during 1983-1993. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  6. The Agency's technical co-operation programme with the United Arab Emirates 1984-1994 country programme summaries

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains a review of the Agency's technical co-operation activities in the United Arab Emirates carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

  7. Co-operation agreement between the European Organization for Nuclear Research (CERN) and the Government of People's Republic of Bangladesh concerning Education, Scientific and Technical Co-operation in High-Energy Physics

    CERN Document Server

    2014-01-01

    Co-operation agreement between the European Organization for Nuclear Research (CERN) and the Government of People's Republic of Bangladesh concerning Education, Scientific and Technical Co-operation in High-Energy Physics

  8. Long Term Operation R and D to Investigate the Technical Basis for Life Extension and License Renewal Decisions

    International Nuclear Information System (INIS)

    Gaertner, John

    2012-01-01

    Establishing an improved technical basis for long term operation of existing plants is a nuclear industry priority. The Electric Power Research Institute (EPRI) has responded with a comprehensive Long Term Operation (LTO) Program addressing this need for existing nuclear power plants world-wide. The program supports both the business decisions necessary to achieve high performance operation and the licensing requirements for operation beyond 60 years. The program selects its R and D priorities in a structured and objective way with much industry input to provide useful results for decisions in the 2014 to 2019 time frame. The program is highly collaborative with U.S. Department of Energy (DOE) and with EPRI-member utilities. The R and D portfolio includes materials aging (metals, concrete, and cables), modernization of information and control technology, enhanced safety analysis, advanced fuel design, demonstration plant activities, life cycle management, and identification of aging management program need for subsequent license renewal. The program has focussed stakeholders world-wide on the technical issues of long term operation, and it is on-track to provide practical results for life extension and license renewal decisions. (author)

  9. Modelling risk in high hazard operations : Integrating technical, organisational and cultural factors

    NARCIS (Netherlands)

    Ale, B.J.M.; Hanea, D.M.; Sillem, S.; Lin, P.H.; Van Gulijk, C.; Hudson, P.T.W.

    2012-01-01

    Recent disasters in high hazard industries such as Oil and Gas Exploration (The Deepwater Horizon) and Petrochemical production (Texas City) have been found to have causes that range from direct technical failures through organizational shortcomings right up to weak regulation and inappropriate

  10. IAEA Technical co-operation. A partner in development. Nuclear science serving people

    International Nuclear Information System (INIS)

    Kinley, D.; Perez Vargaz, J.

    1997-01-01

    This issue contains descriptions of IAEA technical cooperation programs in a variety of disciplines and locations. It includes articles on the eradication of Tsetse flies in Africa, biofertilizers for agriculture, new strains of rice, water resource management, pollution control for a sustainable environment, nuclear medicine, and ensuring nuclear reactor safety

  11. Technical operations procedure for assembly and emplacement of the soil temperature test--test assembly

    International Nuclear Information System (INIS)

    Weber, A.P.

    1978-01-01

    A description is given of the plan for assembly, instrumentation, emplacement, and operational checkout of the soil temperature test assembly and dry well liner. The activities described cover all operations necessary to accomplish the receiving inspection, instrumentation and pre-construction handling of the dry well liner, plus all operations performed with the test article. Actual details of construction work are not covered by this procedure. Each part and/or section of this procedure is a separate function to be accomplished as required by the nature of the operation. The organization of the procedure is not intended to imply a special operational sequence or schedular requirement. Specific procedure operational sections include: receiving inspection; liner assembly operations; construction operations (by others); prepare shield plug; test article assembly and installation; and operational checkout

  12. Quarterly report of the Swedish Nuclear Power Inspectorate. 4th quarter 1984

    International Nuclear Information System (INIS)

    1985-01-01

    During the fourth quarter of 1984 ten power reactors were in operation in Sweden. Two new reactors, Oskarshamn 3 and Forsmark 3, got loading authorization and started the test operation. No serious fault has occurred during the period. (K.A.E.)

  13. Short-term energy outlook. Quarterly projections, 2nd quarter 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-05-01

    The Energy Information Administration (EIA) prepares quarterly, short-term energy supply, demand, and price projections for publication in February, May, August, and November in the Short-Term Energy Outlook (Outlook). An annual supplement analyzes the performance of previous forecasts, compares recent cases with those of other forecasting services, and discusses current topics related to the short-term energy markets. The forecast period for this issue of the Outlook extends from the second quarter of 1994 through the fourth quarter of 1995. Values for the first quarter of 1994, however, are preliminary EIA estimates (for example, some monthly values for petroleum supply and disposition are derived in part from weekly data reported in the Weekly Petroleum Status Report) or are calculated from model simulations using the latest exogenous information available. The historical energy data, compiled into the second quarter 1994 version of the Short-Term Integrated Forecasting System (STIFS) database, are mostly EIA data regularly published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications. Minor discrepancies between the data in these publications and the historical data in this Outlook are due to independent rounding. The STIFS database is archived quarterly and is available from the National Technical Information Service. The cases are produced using the STIFS. The STIFS model is driven principally by three sets of assumptions or inputs: estimates of key macroeconomic variables, world oil price assumptions, and assumptions about the severity of weather. Macroeconomic estimates are produced by DRI/McGraw-Hill but are adjusted by EIA to reflect EIA assumptions about the world price of crude oil, energy product prices, and other assumptions which may affect the macroeconomic outlook. The EIA model is available on computer tape from the National Technical Information Service.

  14. Quarterly environmental data summary for third quarter 1999

    Energy Technology Data Exchange (ETDEWEB)

    McCracken, Stephen H. [Weldon Spring Site, St. Charles, MO (United States)

    1999-11-05

    A copy of the quarterly Environmental Data Summary (QEDS) for the third quarter of 1999 is enclosed. The data, except for air monitoring data and site KPA generated data (uranium analyses), were received from the contract laboratories, verified by the WSSRAP verification group and merged into the data base during the third quarter of 1999. Selected KPA results for on-site total uranium analyses performed during the quarter are also included. Air monitoring data presented are the most recent complete sets of quarterly data.

  15. Development, initial reliability and validity testing of an observational tool for assessing technical skills of operating room nurses.

    Science.gov (United States)

    Sevdalis, Nick; Undre, Shabnam; Henry, Janet; Sydney, Elaine; Koutantji, Mary; Darzi, Ara; Vincent, Charles A

    2009-09-01

    The recent emergence of the Systems Approach to the safety and quality of surgical care has triggered individual and team skills training modules for surgeons and anaesthetists and relevant observational assessment tools have been developed. To develop an observational tool that captures operating room (OR) nurses' technical skill and can be used for assessment and training. The Imperial College Assessment of Technical Skills for Nurses (ICATS-N) assesses (i) gowning and gloving, (ii) setting up instrumentation, (iii) draping, and (iv) maintaining sterility. Three to five observable behaviours have been identified for each skill and are rated on 1-6 scales. Feasibility and aspects of reliability and validity were assessed in 20 simulation-based crisis management training modules for trainee nurses and doctors, carried out in a Simulated Operating Room. The tool was feasible to use in the context of simulation-based training. Satisfactory reliability (Cronbach alpha) was obtained across trainers' and trainees' scores (analysed jointly and separately). Moreover, trainer nurse's ratings of the four skills correlated positively, thus indicating adequate content validity. Trainer's and trainees' ratings did not correlate. Assessment of OR nurses' technical skill is becoming a training priority. The present evidence suggests that the ICATS-N could be considered for use as an assessment/training tool for junior OR nurses.

  16. Qualification of technical personnel for employment during construction and operation of the SSC

    International Nuclear Information System (INIS)

    Johnson, C.D.; Wolf, L.J.

    1991-01-01

    In the early stages of the SSC design it became apparent that construction will have a significant impact on post-secondary technical/vocational education in Texas. Present estimates are that from 2,000 to 3,000 employees will be needed in the traditional fields of civil, mechanical, electrical technology, computers as well as exotic technologies such as cryogenics and high vacuum. In this paper an on-going project is described which is directed toward assuring that graduates of Texas post-secondary technical and vocational education programs will be competitive for employment in these jobs. The project involves development of SSC pedagogical material at a level appropriate to the students, education of teachers about the SSC and development of delivery systems for education about the SSC

  17. Technical water system of the Reactor - Design description, operation regime and manipulation

    International Nuclear Information System (INIS)

    Badrljica, R.

    1984-05-01

    Technical water, reactor secondary coolant system is made of four parts: pumping station on the Danube; sedimentation facility in the village Vinca; coolant, heat exchangers and other elements within the RA reactor building; leading outer pipes and the stream Mlaka. All the four parts are connected to form a functional entirety, and each of them connected to cooling heat exchangers forms a partial functional system which enable the whole system to fulfill its fundamental task [sr

  18. The Agency's Technical Co-operation programme with Cote d'Ivoire, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $1.7 million of Agency support received, Cote d'Ivoire ranks 60th among all recipients of technical assistance in the period 1958 through 1991. Over half of the assistance received during the past ten years has been in the form of equipment (59%), complemented by expert services (26%) and training (15%). The best part of the resources was provided by the Technical Assistance and Co-operation Fund (91%), the remainder was made available through extrabudgetary contributions (7%) and through assistance in kind (2%). During the past ten years, project activities - and disbursements - have concentrated exclusively on three major areas: agriculture (59%), general atomic energy development (30%) and nuclear safety (11%)

  19. The Agency's Technical Co-operation programme with the United Republic of Tanzania, 1982-1992. Country programme summaries

    International Nuclear Information System (INIS)

    1992-01-01

    The country programme summary reported here is one in the series of such studies being undertaken of the Agency's TC programme with Member States. With over $ 3.4 million of Agency support received, the United Republic of Tanzania ranks 44th among all recipients of technical assistance in the period 1958 - 1991. Almost half of the assistance during the past ten years has been provided in the form of equipment (49%), followed by training through fellowships and scientific visits (29%) and expert services (22%). Ninety-two per cent of the resources were provided by the Technical Assistance and Co-operation Fund, the rest was made available through assistance in kind (5%) and through extrabudgetary contributions (3%). With regard to project disbursement by sector, by far the largest share has gone to agriculture (48%), followed by nuclear physics (20%), nuclear safety (17%) and nuclear medicine (11%)

  20. Innovative Clean Coal Technology (ICCT): Demonstration of selective catalytic reduction (SCR) technology for the control of nitrogen oxide (NO{sub x}) emissions from high-sulfur coal-fired boilers. Technical progress report, third and fourth quarters 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    The objective of this project is to demonstrate and evaluate commercially available selective catalytic reduction (SCR) catalysts from U.S., Japanese, and European catalyst suppliers on a high-sulfur U.S. Coal-fired boiler. SCR is a post-combustion nitrogen oxide (NO{sub x}) control technology that involves injecting ammonia into the flue gas generated from coal combustion in an electric utility boiler. The flue gas containing ammonia is then passed through a reactor that contains a specialized catalyst. In the presence of the catalyst, the ammonia reacts with NO{sub x} to form nitrogen and water vapor. Although SCR is widely practiced in Japan and European gas-, oil-, and low-sulfur coal-fired boilers, there are several technical uncertainties associated with applying SCR to U.S. coals. These uncertainties include: (1) potential catalyst deactivation due to poisoning by trace metal species present in U.S. coals that are not present in other fuels; (2) performance of the technology and effects on the balance-of-plant equipment in the presence of high amounts of SO{sub 2} and SO{sub 3}; performance of a wide variety of SCR catalyst compositions, geometries, and methods of manufacture under typical high-sulfur coal-fired utility operating conditions. These uncertainties are being explored by operating a series of small- scale SCR reactors and simultaneously exposing different SCR catalysts to flue gas derived from the combustion of high sulfur U.S. coal. The demonstration is being performed at Gulf Power Company`s Plant Crist Unit No. 5 (75 MW capacity) near Pensacola, Florida. The project is funded by the U.S. Department of Energy (DOE), Southern Company Services, Inc. (SCS on behalf of the entire Southern electric system), the Electric Power Research Institute (EPRI), and Ontario Hydro. SCS is the participant responsible for managing al aspects of this project. 1 ref., 69 figs., 45 tabs.

  1. Technical Note: Continuity of MIPAS-ENVISAT operational ozone data quality from full- to reduced-spectral-resolution operation mode

    Directory of Open Access Journals (Sweden)

    S. Ceccherini

    2008-04-01

    Full Text Available MIPAS (Michelson Interferometer for Passive Atmospheric Sounding is operating on the ENVIronmental SATellite (ENVISAT since March 2002. After two years of nearly continuous limb scanning measurements, at the end of March 2004, the instrument was stopped due to problems with the mirror drive of the interferometer. Operations with reduced maximum path difference, corresponding to both a reduced-spectral-resolution and a shorter measurement time, were resumed on January 2005. In order to exploit the reduction in measurement time, the measurement scenario was changed adopting a finer vertical limb scanning. The change of spectral resolution and of measurement scenario entailed an update of the data processing strategy. The aim of this paper is the assessment of the differences in the quality of the MIPAS ozone data acquired before and after the stop of the operations. Two sets of MIPAS ozone profiles acquired in 2003–2004 (full-resolution measurements and in 2005–2006 (reduced-resolution measurements are compared with collocated ozone profiles obtained by GOMOS (Global Ozone Monitoring by Occultation of Stars, itself also onboard ENVISAT. The continuity of the GOMOS data quality allows to assess a possible discontinuity of the MIPAS performances. The relative bias and precision of MIPAS ozone profiles with respect to the GOMOS ones have been compared for the measurements acquired before and after the stop of the MIPAS operations. The results of the comparison show that, in general, the quality of the MIPAS ozone profiles retrieved from reduced-resolution measurements is comparable or better than that obtained from the full-resolution dataset. The only significant change in MIPAS performances is observed at pressures around 2 unit{hPa}, where the relative bias of the instruments increases by a factor of 2 from the 2003–2004 to 2005–2006 measurements.

  2. EDF - Quarterly Financial Information

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  3. Technical development and operation of TV thomson scattering system on JFT-2M tokamak

    International Nuclear Information System (INIS)

    Shiina, Tomio; Yamauchi, Toshihiko; Ishige, Yoichi

    1998-10-01

    Six years have passed since the TV Thomson scattering system (TVTS) was completed and the operation was started on the JFT-2M tokamak. TVTS was developed in collaboration with Princeton Plasma Physics Laboratory. Many troubles on the hardware are and the software are were encountered. Improvements of the system were needed in each occasion. Phenomena of troubles were carefully analyzed and they have been solved in operating the system. This paper presents thus obtained know-how necessary for the operation of TVTS as well as methods of operation. (author)

  4. Office for Analysis and Evaluation of Operational Data 1996 annual report. Volume 10, Number 3: Technical training

    International Nuclear Information System (INIS)

    1997-12-01

    This annual report of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1996. The report is published in three parts. NUREG-1272, Vol. 10, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports and reports to the NRC's Operations Center. NUREG-1272, Vol. 10, No. 2, covers nuclear materials and presents a review of the events and concerns during 1996 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from CY 1980 through 1996. NUREG-1272, Vol. 10, No. 3, covers technical training and presents the activities of the Technical Training Center in support of the NRC's mission in 1996

  5. The decommissioning of WWER type nuclear power plants. Final report on an IAEA regional technical co-operation project

    International Nuclear Information System (INIS)

    2000-01-01

    Numerous WWER-440 nuclear power plants are in operation in central and eastern Europe and a small number have already been shut down. In addition to reactors already shut down, many other reactors will reach the end of their design lifetime in a few years and become candidates for decommissioning. It is unfortunate that little consideration was devoted to decommissioning of WWER-440 reactors at the plant design and construction stage, and little emphasis was placed on planning for decommissioning. It is within this context that the IAEA launched a regional technical co-operation project in 1994 with the aim of providing guidance on planning and management of decommissioning for WWERs. The project, which had a duration of four years (1995-1998), included the organization of workshops and scientific visits to countries having WWERs and other countries where active decommissioning projects were under way. Eventually, participants suggested the consolidation of expert guidance and collective opinions into a TECDOC, which was drafted by both designated participants from project recipient countries and invited experts. The TECDOC has the aim of serving as a stimulus for all concerned parties in central and eastern European countries to initiate concrete decommissioning planning, including assessment of existing and required resources for the eventual implementation of decommissioning plans. In addition, the regional technical co-operation project has managed to bring together in this TECDOC a number of good practices that could be useful in WWER-440 decommissioning

  6. 25 CFR 216.4 - Technical examination of prospective surface exploration and mining operations.

    Science.gov (United States)

    2010-04-01

    ... mining sites and mining operations vary widely with respect to topography, climate, surrounding land uses... and mining operations. 216.4 Section 216.4 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR ENERGY AND MINERALS SURFACE EXPLORATION, MINING, AND RECLAMATION OF LANDS General Provisions § 216...

  7. Risk-based configuration control: Application of PRA in improving technical specifications and operational safety

    International Nuclear Information System (INIS)

    Samanta, P.K.; Kim, I.S.; Vesely, W.E.

    1991-01-01

    The objective of risk-based configuration control is to detect and control plant configurations form a risk perspective. The configurations of particular interest involve components which are down during power operation. Controlling plant configurations from a risk-perspective can provide more direct risk control and also more operational flexibility by allowing looser control in areas unimportant to risk

  8. Human Factors Analysis of Pipeline Monitoring and Control Operations: Final Technical Report

    Science.gov (United States)

    2008-11-26

    The purpose of the Human Factors Analysis of Pipeline Monitoring and Control Operations project was to develop procedures that could be used by liquid pipeline operators to assess and manage the human factors risks in their control rooms that may adv...

  9. Quarterly Financial Report for the period ending 30 September 2015

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

    Office 2004 Test Drive User

    2015-09-30

    Sep 30, 2015 ... This Management's Discussion and Analysis (MD&A) provides a narrative .... 8 | QUARTERLY FINANCIAL REPORT FOR THE PERIOD 1 JULY TO 30 ... The internally restricted equity for special programs and operational ...

  10. quarterly financial report for the period ending 30 June 2014

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

    Office 2004 Test Drive User

    2014-06-30

    Jun 30, 2014 ... This Management's Discussion and Analysis (MD&A) provides a narrative outlining the financial ... Cost of operations. (33 422) ..... Accounting Standard 34 (Interim Financial Reporting) and the Standard on Quarterly Financial.

  11. Applied Research on Laparoscopic Simulator in the Resident Surgical Laparoscopic Operation Technical Training.

    Science.gov (United States)

    Fu, Shangxi; Liu, Xiao; Zhou, Li; Zhou, Meisheng; Wang, Liming

    2017-08-01

    The purpose of this study was to estimate the effects of surgical laparoscopic operation course on laparoscopic operation skills after the simulated training for medical students with relatively objective results via data gained before and after the practice course of laparoscopic simulator of the resident standardized trainees. Experiment 1: 20 resident standardized trainees with no experience in laparoscopic surgery were included in the inexperienced group and finished simulated cholecystectomy according to simulator videos. Simulator data was collected (total operation time, path length, average speed of instrument movement, movement efficiency, number of perforations, the time cautery is applied without appropriate contact with adhesions, number of serious complications). Ten attending doctors were included in the experienced group and conducted the operation of simulated cholecystectomy directly. Data was collected with simulator. Data of two groups was compared. Experiment 2: Participants in inexperienced group were assigned to basic group (receiving 8 items of basic operation training) and special group (receiving 8 items of basic operation training and 4 items of specialized training), and 10 persons for each group. They received training course designed by us respectively. After training level had reached the expected target, simulated cholecystectomy was performed, and data was collected. Experimental data between basic group and special group was compared and then data between special group and experienced group was compared. Results of experiment 1 showed that there is significant difference between data in inexperienced group in which participants operated simulated cholecystectomy only according to instructors' teaching and operation video and data in experienced group. Result of experiment 2 suggested that, total operation time, number of perforations, number of serious complications, number of non-cauterized bleeding and the time cautery is applied

  12. Mathematical model for estimating of technical and technological indicators of railway stations operation

    Directory of Open Access Journals (Sweden)

    D.M. Kozachenko

    2013-06-01

    Full Text Available Purpose. The article aims to create a mathematical model of the railway station functioning for the solving of problems of station technology development on the plan-schedule basis. Methodology. The methods of graph theory and object-oriented analysis are used as research methods. The model of the station activity plan-schedule includes a model of technical equipment of the station (plan-schedule net and a model of the station functioning , which are formalized on the basis of parametric graphs. Findings. The presented model is implemented as an application to the graphics package AutoCAD. The software is developed in Visual LISP and Visual Basic. Taking into account that the construction of the plan-schedule is mostly a traditional process of adding, deleting, and modifying of icons, the developed interface is intuitively understandable for a technologist and practically does not require additional training. Originality. A mathematical model was created on the basis of the theory of graphs and object-oriented analysis in order to evaluate the technical and process of railway stations indicators; it is focused on solving problems of technology development of their work. Practical value. The proposed mathematical model is implemented as an application to the graphics package of AutoCAD. The presence of a mathematical model allows carrying out an automatic analysis of the plan-schedule and, thereby, reducing the period of its creation more than twice.

  13. Technical report on operating experience with boiling water reactor offgas systems

    International Nuclear Information System (INIS)

    Lo, R.; Barrett, L.; Grimes, B.; Eisenhut, D.

    1978-03-01

    Over 100 reactor years of Boiling Water Reactor (BWR) operating experience have been accumulated since the first commercial operation of BWRs. A number of incidents have occurred involving the ''offgas'' of these Boiling Water Reactors. This report describes the generation and processing of ''offgas'' in Boiling Water Reactors, the safety considerations regarding systems processing the ''offgas'', operating experience involving ignitions or explosions of ''offgas'' and possible measures to reduce the likelihood of future ignitions or explosions and to mitigate the consequences of such incidents should they occur

  14. Investigation into the impact of privatizing civil engineering operations in Louisiana DOTD : [technical summary].

    Science.gov (United States)

    2013-06-01

    This report documents an investigation into the possibility of privatizing the civil engineering operations in the Louisiana Department : of Transportation and Development (DOTD). The study was conducted in response to House Resolution 105 of the Lou...

  15. Compilation of Energy Efficient Concepts in Advanced Aircraft Design and Operations. Volume 1. Technical report

    National Research Council Canada - National Science Library

    Clyman, Milton

    1980-01-01

    .... The search addressed the technologies necessary to support next generation (IOC 1990+) air vehicle design and operation concepts that will reduce the requirement for natural petroleum-derived energy...

  16. US energy industry financial developments, 1991 third quarter

    International Nuclear Information System (INIS)

    1991-01-01

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

  17. The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency. Latest Status (Chinese Edition)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1979-03-15

    The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency were approved by the Board of Governors on 21 February 1979. The test is reproduced herein for the information of all Members. The provisions established by the Board of Governors on 24 September 1977 for the application of safeguards in relation to the granting of technical assistance are also reproduced in the Annex to the Revised Guiding Principles and General Operating Rules.

  18. The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency. Latest Status (Spanish Edition)

    International Nuclear Information System (INIS)

    1979-03-01

    The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency were approved by the Board of Governors on 21 February 1979. The test is reproduced herein for the information of all Members. The provisions established by the Board of Governors on 24 September 1977 for the application of safeguards in relation to the granting of technical assistance are also reproduced in the Annex to the Revised Guiding Principles and General Operating Rules. [es

  19. The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency. Latest Status (Chinese Edition)

    International Nuclear Information System (INIS)

    1979-03-01

    The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency were approved by the Board of Governors on 21 February 1979. The test is reproduced herein for the information of all Members. The provisions established by the Board of Governors on 24 September 1977 for the application of safeguards in relation to the granting of technical assistance are also reproduced in the Annex to the Revised Guiding Principles and General Operating Rules.

  20. The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency. Latest Status (Arabic Edition)

    International Nuclear Information System (INIS)

    1979-03-01

    The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency were approved by the Board of Governors on 21 February 1979. The test is reproduced herein for the information of all Members. The provisions established by the Board of Governors on 24 September 1977 for the application of safeguards in relation to the granting of technical assistance are also reproduced in the Annex to the Revised Guiding Principles and General Operating Rules.

  1. The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency. Latest Status (French Edition)

    International Nuclear Information System (INIS)

    1979-03-01

    The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency were approved by the Board of Governors on 21 February 1979. The test is reproduced herein for the information of all Members. The provisions established by the Board of Governors on 24 September 1977 for the application of safeguards in relation to the granting of technical assistance are also reproduced in the Annex to the Revised Guiding Principles and General Operating Rules. [fr

  2. The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency. Latest Status (Russian Edition)

    International Nuclear Information System (INIS)

    1979-03-01

    The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency were approved by the Board of Governors on 21 February 1979. The test is reproduced herein for the information of all Members. The provisions established by the Board of Governors on 24 September 1977 for the application of safeguards in relation to the granting of technical assistance are also reproduced in the Annex to the Revised Guiding Principles and General Operating Rules. [ru

  3. Improving the action requirements of technical specifications: A risk-comparison of continued operation and plant shutdown

    Energy Technology Data Exchange (ETDEWEB)

    Kim, I.S.; Samanta, P.K. [Brookhaven National Lab., Upton, NY (United States); Mankamo, T.

    1995-04-01

    When the systems needed to remove decay heat are inoperable or degraded, the risk of shutting down the plant may be comparable to, or even higher than, that of continuing power operation with the equipment inoperable while giving priority to repairs. This concern arises because the plant may not have sufficient capability for removing decay heat during the shutdown. However, Technical Specifications (TSs) often require {open_quotes}immediate{close_quotes} shutdown of the plant. In this paper, we present risk-based analyses of the various operational policy alternatives available in such situations, with an example application to the standby service water (SSW) system of a BWR. These analyses can be used to define risk-effective requirements for those standby safety systems under discussion.

  4. Improving the action requirements of technical specifications: A risk-comparison of continued operation and plant shutdown

    International Nuclear Information System (INIS)

    Kim, I.S.; Samanta, P.K.

    1994-01-01

    When the systems needed to remove decay heat are inoperable or degraded, the risk of shutting down the plant may be comparable to, or even higher than, that of continuing power operation with the equipment inoperable while giving priority to repairs. This concern arises because the plant may not have sufficient capability for removing decay heat during the shutdown. However, Technical Specifications (TSs) often require ''immediate'' shutdown of the plant. In this paper, the authors present risk-based analyses of the various operational policy alternatives available in such situations, with an example application to the standby service water (SSW) system of a BWR. These analyses can be used to define risk-effective requirements for those standby safety systems under discussion

  5. Realities of technical co-operation in the peaceful uses of nuclear energy

    International Nuclear Information System (INIS)

    Luxo, A.; Villaros, P.; Naudet, G.

    1978-01-01

    The decision to develop the peaceful uses of nuclear energy, especially the generation of electricity, is usually based - particularly in the developing countries - on numerous considerations, mainly of an economic and political nature. Since the resources of nuclear technology are concentrated, relatively speaking, in the advanced countries, the use of nuclear energy by countries that have decided to go nuclear is based on effective co-operation between the exporting and importing countries. The present paper is intended as an additional contribution to consideration of the realities of such co-operation. The authors first mention the specific features of nuclear development, after which they consider, on the basis thereof, the different forms of co-operation required for the transfer of technological knowhow, and the conditions determining the effectiveness of such transfer. This effectiveness is not linked solely to the competence of the personnel concerned or to smooth organizational procedures, but also to decisive socio-psychological factors. Having analysed these factors, the authors examine the salient problems of co-operation arising during the process of nuclear development. Co-operation ever better adapted to the purpose and taking human considerations into account will enable importing countries to acquire the nuclear knowhow that will promote their economic and social development. (author)

  6. Draft Function Allocation Framework and Preliminary Technical Basis for Advanced SMR Concepts of Operations

    Energy Technology Data Exchange (ETDEWEB)

    Jacques Hugo; John Forester; David Gertman; Jeffrey Joe; Heather Medema; Julius Persensky; April Whaley

    2013-04-01

    This report presents preliminary research results from the investigation in to the development of new models and guidance for concepts of operations (ConOps) in advanced small modular reactor (aSMR) designs. In support of this objective, three important research areas were included: operating principles of multi-modular plants, functional allocation models and strategies that would affect the development of new, non-traditional concept of operations, and the requiremetns for human performance, based upon work domain analysis and current regulatory requirements. As part of the approach for this report, we outline potential functions, including the theoretical and operational foundations for the development of a new functional allocation model and the identification of specific regulatory requirements that will influence the development of future concept of operations. The report also highlights changes in research strategy prompted by confirmationof the importance of applying the work domain analysis methodology to a reference aSMR design. It is described how this methodology will enrich the findings from this phase of the project in the subsequent phases and help in identification of metrics and focused studies for the determination of human performance criteria that can be used to support the design process.

  7. Integrated automatic non-destructive testing in industrial production and in the operation of technical plant

    International Nuclear Information System (INIS)

    Hoeller, P.

    1989-01-01

    The article deals with non-destructive testing (NDT) in automated manufacture and in the automated operation of industrial plant. In both areas of application, the tests are coupled to the process (real time operation) and the results are used for the control of manufacture or of the course of the process. The control process can be coupled to the process in open loop or closed loop. The subject is explained by the following examples: 1) Automated testing of sheets in a steelworks. 2) Automatic NDT on machine parts in tempering and machining by the 3MA system (3MA: micro-magnetic, multi-parameter, micro-structure and stress analysis). 3) Automated ultrasonic testing in manufacture and in the operation of plants with the ALOK data collection and processing system (ALOK: amplitude, running time, location curves). 4) Automated wheel running surface test on Intercity experimental train, and 5) automated level measurement on BWR pressure vessels. (orig./MM) [de

  8. Operational Features of the Kamehameha Early Education Project. Technical Report #4.

    Science.gov (United States)

    Gallimore, Ronald; And Others

    This report summarizes the operational features of the initial phases of the Kamehameha Early Education Project (KEEP). The rationale for KEEP's focus on conducting research on programs similar to those in the public schools rather than on developing radically innovative educational programs is discussed. Start up procedures such as recruitment of…

  9. Enhanced technical and economic working domains of industrial heat pumps operated in series

    DEFF Research Database (Denmark)

    Ommen, Torben; Jensen, Jonas Kjær; Markussen, Wiebke Brix

    2015-01-01

    By operating heat pumps (HPs) in series, it is possible to obtain closer match between working fluid and sink- and source streams, resulting in higher coefficient of performance (COP). For industrial HPs, it was found that serial connection of either two or three units results in an increase in COP...

  10. Concept Specification by PRECIS Role Operators: Some Technical Problems with Social Science and Humanities Literature.

    Science.gov (United States)

    Mahapatra, M.; Biswas, S. C.

    1985-01-01

    Two hundred journal articles related to fields of taxation, genetic psychology, and Shakespearean drama published from 1970-1980 were analyzed and PRECIS input strings were drawn. Occasions when input string and index entries looked incomplete and unexpressive after losing context of document are provided with solutions. Role operator schema is…

  11. 77 FR 30585 - Operating Limitations at New York LaGuardia Airport; Technical Amendment

    Science.gov (United States)

    2012-05-23

    ... the High Density Rule of FAA slot exemption rules as of January 1, 2007; to the primary marketing air... transaction. However, the FAA will approve transfers between carriers under the same marketing control up to 5.... Unscheduled operations include general aviation, public aircraft, military, charter, ferry, and positioning...

  12. 77 FR 24950 - Midwest Independent Transmission, System Operator, Inc.; Supplemental Notice of Technical Conference

    Science.gov (United States)

    2012-04-26

    ... Conference. The Midwest Independent Transmission System Operator, Inc. (MISO) and/or Potomac Economics, Inc... that is less than 50 percent of the applicable Reference Level. Provide a justification for this... committed? Please explain. b. Can units committed based on economics in the SCUC and SCED processes be...

  13. Military Curricula for Vocational & Technical Education. Club Restaurant Operations, Part II, 9-10.

    Science.gov (United States)

    Army Quartermaster School, Ft. Lee, VA.

    These programmed instructional materials for part 2 of a secondary-postsecondary subcourse in club management operations are one of a number of military-developed curriculum packages selected for adaptation to vocational instruction and curriculum development in civilian settings. This part of the subcourse consists of three lessons and an…

  14. Military Curricula for Vocational & Technical Education. Club Restaurant Operations, Part I, 9-9.

    Science.gov (United States)

    Army Quartermaster School, Ft. Lee, VA.

    These reading materials, self-test reviews, and examination for part 1 of a secondary-postsecondary subcourse in club management operations are one of a number of military-developed curriculum packages selected for adaptation to vocational instruction and curriculum development in civilian settings. Five lessons focusing on two topics are included…

  15. Operation, Maintenance and Management of Wastewater Treatment Facilities: A Bibliography of Technical Documents.

    Science.gov (United States)

    Himes, Dottie

    This is an annotated bibliography of wastewater treatment manuals. Fourteen manuals are abstracted including: (1) A Planned Maintenance Management System for Municipal Wastewater Treatment Plants; (2) Anaerobic Sludge Digestion, Operations Manual; (3) Emergency Planning for Municipal Wastewater Treatment Facilities; (4) Estimating Laboratory Needs…

  16. Quarterly environmental radiological survey summary: Second Quarter 1995 100, 200, 300, and 600 Areas

    International Nuclear Information System (INIS)

    McKinney, S.M.

    1995-01-01

    This report provides a summary of the radiological surveys performed in support of the operational environmental monitoring program at the Hanford Site. The Second Quarter 1995 survey results and the status of actions required from current and past reports are summarized

  17. Quarterly environmental radiological survey summary. Fourth quarter, 1995 100, 200, 300, and 600 Areas

    International Nuclear Information System (INIS)

    McKinney, S.M.; Markes, B.M.

    1996-01-01

    This report provides a summary of the radiological surveys performed in support of the operational environmental monitoring program at the Hanford Site. The Fourth Quarter 1995 survey results and the status of actions required from current and past reports are described

  18. Technical considerations in repowering a nuclear plant for fossil fueled operation

    International Nuclear Information System (INIS)

    Patti, F.J.

    1996-01-01

    Repowering involves replacement of the reactor by a fossil fuel source of steam. This source can be a conventional fossil fueled boiler or the heat recovery steam generator (HRSG) on a gas turbine exhaust. The existing steam turbine plant is used to the extent possible. Alternative fuels for repowering a nuclear plant are coal, natural gas and oil. In today's world oil is not usually an alternative. Selection of coal or natural gas is largely a matter of availability of the fuel near the location of the plant. Both the fossil boiler and the HRSG produce steam at higher pressures and temperatures than the throttle conditions for a saturated steam nuclear turbine. It is necessary to match the steam conditions from the new source to the existing turbine as closely as possible. Technical approaches to achieve a match range from using a topping turbine at the front end of the cycle to attemperation of the throttle steam with feedwater. The electrical output from the repowered plant is usually greater than that of the original nuclear fueled design. This requires consideration of the ability to use the excess electricity. Interfacing of the new facility with the existing turbine plant requires consideration of facility layout and design. Site factors must also be considered, especially for a coal fired boiler, since rail and coal handling facilities must be added to a site for which these were not considered. Additional site factors that require consideration are ash handling and disposal

  19. Operators Manual and Technical Reference for the Z-Beamlet Phase Modulation Failsafe System: Version 1.

    Energy Technology Data Exchange (ETDEWEB)

    Armstrong, Darrell J.

    2014-09-01

    The need for pulse energies exceeding 4 kJ and pulse lengths [?] 2 ns in Sandia's Z-Beamlet laser (ZBL) requires that the single-frequency spectrum of its fiber-laser master oscillator be converted to a phase modulated spectrum with a modulation in dex [?] 5. Because accidental injection of single-frequency light into ZBL could result i n damage to optical materials from transverse stimulated Brillouin scattering, the presence of phase modulated (PM) light must be monitored by a reliable failsafe system that can stop a las er shot within of a few 10's of ns following a failure of the PM system. This requirement is met by combining optical heterodyne detection with high-speed electronics to indicate the pres ence or absence of phase modulated light. The transition time for the failsafe signal resultin g from a sudden failure using this technique is approximately 35 ns. This is sufficiently short to safely stop a single-frequency laser pulse from leaving ZBL's regenerative amplifier with a n approximately 35 ns margin of safety. This manual and technical reference contains detai led instructions for daily use of the PM failsafe system and provides enough additional informat ion for its maintenance and repair.

  20. Human Factors and Technical Considerations for a Computerized Operator Support System Prototype

    Energy Technology Data Exchange (ETDEWEB)

    Ulrich, Thomas Anthony [Idaho National Lab. (INL), Idaho Falls, ID (United States); Lew, Roger Thomas [Idaho National Lab. (INL), Idaho Falls, ID (United States); Medema, Heather Dawne [Idaho National Lab. (INL), Idaho Falls, ID (United States); Boring, Ronald Laurids [Idaho National Lab. (INL), Idaho Falls, ID (United States); Thomas, Kenneth David [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    A prototype computerized operator support system (COSS) has been developed in order to demonstrate the concept and provide a test bed for further research. The prototype is based on four underlying elements consisting of a digital alarm system, computer-based procedures, PI&D system representations, and a recommender module for mitigation actions. At this point, the prototype simulates an interface to a sensor validation module and a fault diagnosis module. These two modules will be fully integrated in the next version of the prototype. The initial version of the prototype is now operational at the Idaho National Laboratory using the U.S. Department of Energy’s Light Water Reactor Sustainability (LWRS) Human Systems Simulation Laboratory (HSSL). The HSSL is a full-scope, full-scale glass top simulator capable of simulating existing and future nuclear power plant main control rooms. The COSS is interfaced to the Generic Pressurized Water Reactor (gPWR) simulator with industry-typical control board layouts. The glass top panels display realistic images of the control boards that can be operated by touch gestures. A section of the simulated control board was dedicated to the COSS human-system interface (HSI), which resulted in a seamless integration of the COSS into the normal control room environment. A COSS demonstration scenario has been developed for the prototype involving the Chemical & Volume Control System (CVCS) of the PWR simulator. It involves a primary coolant leak outside of containment that would require tripping the reactor if not mitigated in a very short timeframe. The COSS prototype presents a series of operator screens that provide the needed information and soft controls to successfully mitigate the event.

  1. Idaho National Laboratory Quarterly Event Performance Analysis FY 2013 4th Quarter

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth A. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2013-11-01

    This report is published quarterly by the Idaho National Laboratory (INL) Performance Assurance Organization. The Department of Energy Occurrence Reporting and Processing System (ORPS) as prescribed in DOE Order 232.2 “Occurrence Reporting and Processing of Operations Information” requires a quarterly analysis of events, both reportable and not reportable for the previous twelve months. This report is the analysis of occurrence reports and deficiency reports (including not reportable events) identified at the Idaho National Laboratory (INL) during the period of October 2012 through September 2013.

  2. Idaho National Laboratory Quarterly Performance Analysis - 2nd Quarter FY2014

    Energy Technology Data Exchange (ETDEWEB)

    Lisbeth A. Mitchell

    2014-06-01

    This report is published quarterly by the Idaho National Laboratory (INL) Performance Assurance Organization. The Department of Energy Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of occurrence reports and other deficiency reports (including not reportable events) identified at INL from January 2014 through March 2014.

  3. Natural gas consumption for GRTgaz areas: 1. Quarter of 2015, 2. Quarter of 2015, 3. Quarter of 2015, 4. Quarter of 2015

    International Nuclear Information System (INIS)

    2016-01-01

    GRTgaz is a European leader in natural gas transmission, a world expert in gas transmission networks and systems, and an operator firmly committed to the energy transition. It owns and operates the gas transmission network throughout most of France and it manages the transmission network in Germany, thereby helping to ensure correct operation of the French and European gas market. It contributes to the energy security of regional supply systems and performs a public service mission to ensure the continuity of consumer supply. This document presents the quarterly key figures of GRTgaz activity in 2015: gross consumption, climate corrected consumption, quantities of natural gas transported

  4. Natural gas consumption within GRTgaz's territory: 1. Quarter of 2008, 2. Quarter of 2008, 3. Quarter of 2008, 4. Quarter of 2008

    International Nuclear Information System (INIS)

    2009-01-01

    GRTgaz is a European leader in natural gas transmission, a world expert in gas transmission networks and systems, and an operator firmly committed to the energy transition. It owns and operates the gas transmission network throughout most of France and it manages the transmission network in Germany, thereby helping to ensure correct operation of the French and European gas market. It contributes to the energy security of regional supply systems and performs a public service mission to ensure the continuity of consumer supply. This document presents the quarterly key figures of GRTgaz activity in 2008: gross consumption, climate corrected consumption, quantities of natural gas transported

  5. Natural gas consumption for GRTgaz areas: 1. Quarter of 2014, 2. Quarter of 2014, 3. Quarter of 2014, 4. Quarter of 2014

    International Nuclear Information System (INIS)

    2015-01-01

    GRTgaz is a European leader in natural gas transmission, a world expert in gas transmission networks and systems, and an operator firmly committed to the energy transition. It owns and operates the gas transmission network throughout most of France and it manages the transmission network in Germany, thereby helping to ensure correct operation of the French and European gas market. It contributes to the energy security of regional supply systems and performs a public service mission to ensure the continuity of consumer supply. This document presents the quarterly key figures of GRTgaz activity in 2014: gross consumption, climate corrected consumption, quantities of natural gas transported

  6. Natural gas consumption for GRTgaz areas: 1. Quarter of 2011, 2. Quarter of 2011, 3. Quarter of 2011, 4. Quarter of 2011

    International Nuclear Information System (INIS)

    2012-01-01

    GRTgaz is a European leader in natural gas transmission, a world expert in gas transmission networks and systems, and an operator firmly committed to the energy transition. It owns and operates the gas transmission network throughout most of France and it manages the transmission network in Germany, thereby helping to ensure correct operation of the French and European gas market. It contributes to the energy security of regional supply systems and performs a public service mission to ensure the continuity of consumer supply. This document presents the quarterly key figures of GRTgaz activity in 2011: gross consumption, climate corrected consumption, quantities of natural gas transported

  7. Idaho National Laboratory Quarterly Performance Analysis - 1st Quarter FY2015

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth A. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-03-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 73 reportable events (27 from the 1St Qtr FY-15 and 46 from the prior three reporting quarters), as well as 38 other issue reports (including nine not reportable events and Significant Category A and B conditions reported during the1st Qtr FY-15) identified at INL during the past 12 months.

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

    Energy Technology Data Exchange (ETDEWEB)

    None

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Entingh, Daniel J.

    1980-03-01

    The Johns Hopkins University Applied Physics Laboratory, under contracts with several agencies of the federal government and an agency of the State of Maryland, is engaged in developing energy resources, utilization concepts, and monitoring and storage methods. This Quarterly Report summarizes the work on the various tasks as of 31 March 1980. The Energy Quarterly Report is divided into four sections. The first, Geothermal Energy Development Planning and Technical Assistance, supported by the Department of Energy/Division of Geothermal Energy (DOE/DGE), contains reports on the progress of geothermal-related tasks on which effort was concentrated during the quarter. The second section, Operational Research, Hydroelectric Power Development, supported by the Department of Energy/Resource Applications (DOE/DGE), contains reports on small-scale hydroelectric investigations in the southeastern states. The third section, Seismotectonic Investigation, supported by the Reactor Safety Research Division of the Nuclear Regulatory Commission, reports on a neotectonic investigation in Connecticut. The fourth section, Energy Conversion and Storage Techniques, contains two articles, the first on OTEC core unit testing supported by the Department of Energy/Division of Central Solar Technology (DOE/CST), and the second on an analysis of the Community Annual Storage Energy System at the U.S. Naval Air Station, Norfolk, Va. This work is supported by the Department of Energy and the Department of Defense, Naval Facilities Engineering Command/Atlantic Division.

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

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-06-01

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

  11. Application and development of probabilistic safety assessment for nuclear power plant operations. Report of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    The Technical Committee Meeting on Procedures for Use of PSA for Optimizing Operational Limits and Conditions for Nuclear Power Plants was held in Barcelona from 20 to 23 September 1993 to serve as a forum for discussion of the development of methods and approaches for PSA applications. The meeting was co-sponsored by the IAEA and the Asco and Vandellos nuclear power plants in Spain and was attended by more than 85 participants from 23 countries. The 35 papers and presentations reflected the extent of activities in this area worldwide. Most of the papers discuss PSA application programmes and/or specific methods and approaches used. This TECDOC, which was prepared by the participants of the Technical Committee meeting, summarizes the insights gained from the papers and plenary discussions. It also presents the conclusions of the work of three working groups which discussed the advantages and limitations of specific aspects of PSA. It provides an up-to-date description of computerized tools for risk monitoring in used or under development in Member States. It is hoped that this report will be a useful source of information on PSA applications. Refs, figs, tabs.

  12. Method for the determination of technical specifications limiting temperature in EBR-II operation

    International Nuclear Information System (INIS)

    Chang, L.K.; Hill, D.J.; Ku, J.Y.

    1994-01-01

    The methodology and analysis procedure to qualify the Mark-V and Mark-VA fuels for the Experimental Breeder Reactor II are summarized in this paper. Fuel performance data and design safety criteria are essential for thermal-hydraulic analysis and safety evaluations. Normal and off-normal operation duty cycles and transient classifications are required for the safety assessment of the fuels. The temperature limits of subassemblies were first determined by a steady-state thermal-structural and fuel damage analysis, in which a trial-and-error approach was used to predict the maximum allowable fuel pin temperature that satisfies the design criteria for steady-state normal operation. The steady-state temperature limits were used as the basis of the off-normal transient analysis to assess the safety performance of the fuel for anticipated, unlikely and extremely unlikely events. If the design criteria for the off-normal events are not satisfied, then the subassembly temperature limit is reduced and an iterative procedure is employed until all design criteria are met

  13. The Posterior Transpetrosal Approach in a Case of Large Retrochiasmatic Craniopharyngioma: Operative Video and Technical Nuances.

    Science.gov (United States)

    Labidi, Moujahed; Watanabe, Kentaro; Loit, Marie-Pier; Hanakita, Shunya; Froelich, Sébastien

    2018-02-01

    Objectives  To discuss the use of the posterior petrosal approach for the resection of a retrochiasmatic craniopharyngioma. Design  Operative video. Results  In this case video, the authors discuss the surgical management of a large craniopharyngioma, presenting with mass effect on the third ventricle and optic apparatus. A first surgical stage, through an endoscopic endonasal transtubercular approach, allowed satisfactory decompression of the optic chiasma and nerves in preparation for adjuvant therapy. However, accelerated growth of the tumor, with renewed visual deficits and mass effect on the hypothalamus and third ventricle, warranted a supplementary resection. A posterior transpetrosal 1 2 (also called "retrolabyrinthine transtentorial") was performed to obtain a better exposure of the tumor and the surrounding anatomy (floor and walls of the third ventricle, perforating vessels, optic nerves, etc.) 3 . Nuances of technique and surgical pearls related to the posterior transpetrosal are discussed and illustrated in this operative video, including the posterior mobilization of the transverse-sigmoid sinuses junction, preservation of the venous anatomy during the tentorial incision, identification and preservation of the floor of the third ventricle during tumor resection, and a careful multilayer closure. Conclusion  Retrochiasmatic craniopharyngiomas are difficult to reach tumors that often require skull base approaches, either endoscopic endonasal or transcranial. The posterior transpetrosal approach is an important part of the surgical armamentarium to safely resect these complex tumors. The link to the video can be found at: https://youtu.be/2MyGLJ_v1kI .

  14. Sales revenue and data for the first quarter of 2007

    International Nuclear Information System (INIS)

    2007-04-01

    This document presents the Areva Group sales revenue and data for the first quarter of 2007: sales revenue stable at 2.47 billion Euro and anticipation of a significant increase in sales revenue for 2007. Other information concerns: the business trends (reform of the nuclear sector in Russia, Toshiba's acquisition of Westinghouse, reopening of the debate on the need to build new nuclear reactors by more than 60 countries), key events concerning Areva's operations during the first quarter (major marketing events, contracts and agreements, strategic developments), and detailed first quarter 2007 sales revenues (front-end division, reactors and services, back-end division, transmission and distribution division). (J.S.)

  15. Technical work plan for Surface Impoundments Operable Unit engineering support studies

    International Nuclear Information System (INIS)

    1995-11-01

    This document provides a comprehensive work plan which, when utilized as a data collection guide for field activities, will provide the necessary information required to complete a report on geotechnical properties of the sediments contained in the Surface Impoundments Operable Unit at Oak Ridge National Laboratory in Oak Ridge, Tennessee. Detailed guidance is provided for the following activities: collection of samples from the impoundments; compressive strength testing of the raw sediments; compressive strength testing of the structurally modified (lime and cement additives) sediments; testing for sediment physical properties and settling rates; testing for sediment dewatering characteristics; testing for radiation activity during the field work; testing for polymer additions that may enhance settling. The work plan additionally provides guidance and examples for the preparation of documents necessary to establish readiness for safe and satisfactory performance of the field activities. An outline for the format requested for a report of these data is also provided

  16. Technical work plan for Surface Impoundments Operable Unit engineering support studies

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    This document provides a comprehensive work plan which, when utilized as a data collection guide for field activities, will provide the necessary information required to complete a report on geotechnical properties of the sediments contained in the Surface Impoundments Operable Unit at Oak Ridge National Laboratory in Oak Ridge, Tennessee. Detailed guidance is provided for the following activities: collection of samples from the impoundments; compressive strength testing of the raw sediments; compressive strength testing of the structurally modified (lime and cement additives) sediments; testing for sediment physical properties and settling rates; testing for sediment dewatering characteristics; testing for radiation activity during the field work; testing for polymer additions that may enhance settling. The work plan additionally provides guidance and examples for the preparation of documents necessary to establish readiness for safe and satisfactory performance of the field activities. An outline for the format requested for a report of these data is also provided.

  17. Summary of field operations Technical Area I well PGS-1. Site-Wide Hydrogeologic Characterization Project

    International Nuclear Information System (INIS)

    Fritts, J.E.; McCord, J.P.

    1995-02-01

    The Environmental Restoration (ER) Project at Sandia National Laboratories, New Mexico is managing the project to assess and, when necessary, to remediate sites contaminated by the lab operations. Within the ER project, the site-wide hydrogeologic characterization task is responsible for the area-wide hydrogeologic investigation. The purpose of this task is to reduce the uncertainty about the rate and direction of groundwater flow beneath the area and across its boundaries. This specific report deals with the installation of PGS-1 monitoring well which provides information on the lithology and hydrology of the aquifer in the northern area of the Kirtland Air Force Base. The report provides information on the well design; surface geology; stratigraphy; structure; drilling, completion, and development techniques; and borehole geophysics information

  18. A rookie's guide to Booster operations. Booster technical note no. 231

    Energy Technology Data Exchange (ETDEWEB)

    Zeno, K. [Brookhaven National Lab. (BNL), Upton, NY (United States). Alternating Gradient Synchrotron Dept.

    1998-09-29

    The purpose of the Booster is to act as an injector for the AGS. It accelerates both protons and other ions. Proton acceleration is distinguished from the acceleration of other ions for several reasons. First, the experimental physics associated with protons, called High Energy Physics is different than that associated with other Ions, called Heavy Ion Physics. From the machine perspective, the process of injection of so called Heavy Ions (ions which are not protons), is distinctly different, from that of protons. A different preinjector, or injector for the Booster, is used for each case. For Protons, a 200 MeV Linear accelerator (The Linac) serves as a preinjector; for Heavy Ions, the Tandem Van De Graaf (The Tandem) is the preinjector. An attribute of the circulating beam which determines to a large degree what problems and what type of machine setup is involved is the beam intensity. The author's focus in this guide is on trying to convey the knowledge and experience involved in the operation of the Booster. Many of the problems encountered can be traced back to equipment failures, often power supplies. Although diagnostics are used, there can also be issues with the controls system itself. Problems with the controls system and prevent fixing or even finding a problem with a machine. The issue of improving a machines' performance can often involve trial and error and observations. The hard part is finding the relationships between things in the day to day operation of the machine. Abstractions about physics, information about controls and instrumentation, and purely empirical observations of how the machine behaves are all part of it.

  19. IAEA Technical Co-operation activities: Asia and the Pacific. Workshop on training nuclear laboratory technicians

    International Nuclear Information System (INIS)

    Roeed, S.S.

    1976-01-01

    The workshop was held to exchange information on existing facilities and programmes in Asia and the Pacific for training nuclear laboratory technicians, to identify future training needs and to assess the need for IAEA's involvement in this field. As the participants outlined the requirements for nuclear laboratory technician training and the facilities available in their respective countries, it became evident that, in addition to the training of radioisotope laboratory technicians, they also wished to review the need for technician training for the operation of nuclear power plants and industrial application of atomic energy. The terms of reference of the workshop were extended accordingly. The opening address by Chang Suk Lee, the Korean Vice Minister of Science and Technology, noted the valuable contribution to quality control and other industrial uses that nuclear techniques have made in his country. He also reviewed the application of nuclear techniques in Korean agriculture and medicine. The participants explored various forms of co-operation that could be established between countries of the region. Exchange programmes, not only for students but also for expert teachers, and the exchange or loan of equipment were suggested. It was felt that some generalized training courses could be organized on a regional basis, and two countries advocated the setting up of a regional training centre. One suggestion was to arrange regional training courses in special fields that would move from one country to another. The need was felt for periodic regional meetings on training methods, course content and other questions relating to training of laboratory technicians. The IAEA was requested to act as a clearinghouse for information on available training facilities in the region and to advise on the curricula for technician training courses. The Agency was also asked to organize short courses for the training of instructors of technicians in the various fields of atomic

  20. Results on Technical and Consultants Service Meetings on Lessons Learned from Operating Experience in Wet and Dry Spent Fuel Storage

    International Nuclear Information System (INIS)

    White, B.; Zou, X.

    2015-01-01

    Spent fuel storage has been and will continue to be a vital portion of the nuclear fuel cycle, regardless of whether a member state has an open or closed nuclear fuel cycle. After removal from the reactor core, spent fuel cools in the spent fuel pool, prior to placement in dry storage or offsite transport for disposal or reprocessing. Additionally, the inventory of spent fuel at many reactors worldwide has or will reach the storage capacity of the spent fuel pool; some facilities are alleviating their need for additional storage capacity by utilizing dry cask storage. While there are numerous differences between wet and dry storage; when done properly both are safe and secure. The nuclear community shares lessons learned worldwide to gain knowledge from one another’s good practices as well as events. Sharing these experiences should minimize the number of incidents worldwide and increase public confidence in the nuclear industry. Over the past 60 years, there have been numerous experiences storing spent fuel, in both wet and dry mediums, that when shared effectively would improve operations and minimize events. These lessons learned will also serve to inform countries, who are new entrants into the nuclear power community, on designs and operations to avoid and include as best practices. The International Atomic Energy Agency convened a technical and several consultants’ meetings to gather these experiences and produce a technical document (TECDOC) to share spent fuel storage lessons learned among member states. This paper will discuss the status of the TECDOC and briefly discuss some lessons learned contained therein. (author)