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.

Mixed Waste Management Facility (MWMF) groundwater monitoring report: Third quarter 1993

Energy Technology Data Exchange (ETDEWEB)

1993-12-01

During third quarter 1993, eight constituents exceeded final Primary Drinking Water Standards in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility, the Old Burial Ground, the E-Area Vaults, and the proposed Hazardous Waste/Mixed Waste Disposal Vaults. As in previous quarters, tritium and trichloroethylene were the most widespread constituents Chloroethene (vinyl chloride), 1,1-dichloroethylene, dichloromethane (methylene chloride), lead, mercury, or tetrachloroethylene also exceeded standards in one or more wells. The elevated constituents were found in Aquifer Zone IIB{sub 2} (Water Table) and Aquifer Zone IIB{sub 1} (Barnwell/McBean) wells. No elevated constituents were exhibited in Aquifer Unit IIA (Congaree) wells. The groundwater flow directions and rates in the three hydrostratigraphic units were similar to those of previous quarters.

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

Energy Technology Data Exchange (ETDEWEB)

1993-06-01

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

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

International Nuclear Information System (INIS)

1994-12-01

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

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.

Results for the Fourth Quarter Calendar Year 2015 Tank 50H Salt Solution Sample

Energy Technology Data Exchange (ETDEWEB)

Crawford, C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-01-11

In this memorandum, the chemical and radionuclide contaminant results from the Fourth Quarter Calendar Year 2015 (CY15) sample of Tank 50H salt solution are presented in tabulated form. The Fourth Quarter CY15 Tank 50H samples were obtained on October 29, 2015 and received at Savannah River National Laboratory (SRNL) on October 30, 2015. The information from this characterization will be used by Defense Waste Processing Facility (DWPF) & Saltstone Facility Engineering for the transfer of aqueous waste from Tank 50H to the Salt Feed Tank in the Saltstone Production Facility, where the waste will be treated and disposed of in the Saltstone Disposal Facility. This memorandum compares results, where applicable, to Saltstone Waste Acceptance Criteria (WAC) limits and targets. Data pertaining to the regulatory limits for Resource Conservation and Recovery Act (RCRA) metals will be documented at a later time per the Task Technical and Quality Assurance Plan (TTQAP) for the Tank 50H saltstone task. The chemical and radionuclide contaminant results from the characterization of the Fourth Quarter Calendar Year 2015 (CY15) sampling of Tank 50H were requested by SRR personnel and details of the testing are presented in the SRNL Task Technical and Quality Assurance Plan.

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.

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.

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

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

Quarterly report on Defense Nuclear Facilities Safety Board Recommendation 90-7

International Nuclear Information System (INIS)

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

1991-10-01

This is the second quarterly report on the progress of activities addressing safety issues associated with Hanford Site high-level radioactive waste tanks that contain ferrocyanide compounds. An implementation plan (Cash 1991) responding to the Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990) was issued in March 1991 describing the activities planned and underway to address each of the six parts of the recommendation. All of the activities listed in the implementation plan are underway, including the multifunctional instrument tree and infrared tasks which resumed in late July. Although technical difficulties and resource limitations delayed some work, noteworthy progress has been made in completing a number of ferrocyanide program milestones. Thermal modeling shows that the heat loading of tank 241-BY-104 is much lower than previously listed and that significant hot spots within the waste are highly unlikely, if not possible. Computerized continuous temperature monitoring was installed on schedule on five of the highest interest tanks and five additional tanks will be on-line in December. Tank intrusive sampling is proceeding and the first vapor samples were obtained in mid-October. Spectral scans were completed for twelve tanks and substantial progress was made on design of an infrared scanning system. Chemical reaction studies are underway with synthetic ferrocyanide compounds believed to be more representative of the ferrocyanide materials actually deposited in the tanks. Tests indicate that water plays a major role in impeding a possible runaway reaction. An emergency planning exercise was conducted in May, emergency procedures were updated this quarter, and validation of the procedures and a second emergency exercise is scheduled for October

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

International Nuclear Information System (INIS)

1996-03-01

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

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

International Nuclear Information System (INIS)

1997-03-01

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

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

International Nuclear Information System (INIS)

Chase, J.

1999-01-01

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

M-Area hazardous waste management facility groundwater monitoring report -- first quarter 1994. Volume 1

International Nuclear Information System (INIS)

Evans, C.S.; Washburn, F.; Jordan, J.; Van Pelt, R.

1994-05-01

This report describes the groundwater monitoring and corrective action program at the M-Area Hazardous Waste Management Facility (HWMF) at the Savannah River Site (SRS) during first quarter 1994 as required by South Carolina Hazardous Waste Permit SC1-890-008-989 and section 264.100(g) of the South Carolina Hazardous Waste Management Regulations. During first quarter 1994, 42 point-of-compliance (POC) wells at the M-Area HWMF were sampled for drinking water parameters

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.

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)

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-02-01

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

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

Mixed Waste Management Facility (MWMF) groundwater monitoring report. Fourth quarter 1993 and 1993 summary

Energy Technology Data Exchange (ETDEWEB)

Butler, C.T.

1994-03-01

During fourth quarter 1993, 10 constituents exceeded final Primary Drinking Water Standards in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility, the Old Burial Ground, the E-Area Vaults, and the proposed Hazardous Waste/Mixed Waste Disposal Vaults. As in previous quarters, tritium and trichloroethylene were the most widespread elevated constituents. Carbon tetrachloride, chloroform, chloroethane (vinyl chloride), 1,1-dichloroethylene, dichloromethane (methylene chloride), lead, mercury, or tetrachloroethylene also exceeded standards in one or more wells. Elevated constituents were found in numerous Aquifer Zone 2B{sub 2} (Water Table) and Aquifer Zone 2B{sub 1}, (Barnwell/McBean) wells and in two Aquifer Unit 2A (Congaree) wells. The groundwater flow direction and rates in the three hydrostratigraphic units were similar to those of previous quarters.

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

Energy Technology Data Exchange (ETDEWEB)

1993-03-01

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

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

Fast Breeder Blanket Facility. Quarterly progress report, July 1, 1978--September 30, 1978

International Nuclear Information System (INIS)

Clikeman, F.M.

1978-09-01

This quarterly progress report summarizes work done at Purdue University's Fast Breeder Blanket Facility for the Department of Energy during the months July to September 1978. The summary includes reports on the models and methods used to characterize the FBBF facility. Using the reported models and calculational methods and computer codes a new cross section set has been generated, self-shielded for 300 0 K for use in all FBBF calculations using the 2DB computer code. The summary includes reports of the reproducability of foil activation data and measurements of the azmuthal symmetry of the facility. The status of the development of technique for the experimental measurements and preliminary foil activation measurements are also reviewed

Power Systems Development Facility. Quarterly report, July--September 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-11-01

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 fimction of particle size, and scale-up of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the original Transport Reactor gas source and hot gas cleanup units: carbonizer/pressurized circulating fluidized bed gas source; hot gas cleanup units to mate to all gas streams; combustion gas turbine; and fuel cell and associated gas treatment. 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 towards completion and integrating the balance-of-plant processes and particulate control devices (PCDS) into the structural and process designs. Substantial progress in construction activities was achieved during the quarter. Delivery and construction of the process structural steel is nearing completion. Nearly all equipment are set in its place and the FW equipment and the PCDs are being set in the structure.

Trend chart: biogas. Forth quarter 2016

International Nuclear Information System (INIS)

Cavaud, Denis

2017-02-01

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

Trend chart: biogas. Second quarter 2016

International Nuclear Information System (INIS)

Cavaud, Denis

2016-08-01

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

Trend chart: biogas. Third quarter 2016

International Nuclear Information System (INIS)

Cavaud, Denis

2016-11-01

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

Trend chart: biogas. First quarter 2016

International Nuclear Information System (INIS)

Cavaud, Denis

2016-05-01

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

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

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

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.

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.

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

Technical Evaluation of Oak Ridge Filter Test Facility

CERN Document Server

Kriskovich, J R

2002-01-01

Two evaluations of the Oak Ridge Department of Energy (DOE) Filter Test Facility (FTF) were performed on December 11 and 12, 2001, and consisted of a quality assurance and a technical evaluation. This report documents results of the technical evaluation.

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

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.

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-02-01

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

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.

Technical specifications for the Pajarito Site Critical Experiments Facility

International Nuclear Information System (INIS)

Malenfant, R.E.; Paxton, H.C.

1980-12-01

This document is to satisfy the requirement for technical specifications spelled out in DOE Manual Chapter 0540, Safety of DOE-Owned Reactors. Technical specifications are defined in Sec. 0540-048, and the requirement for them appears in Sec. 0540-015. The following technical specifications update the document, Technical Specifications for the Pajarito Site Critical Experiments Facility

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-01-01

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

Technical progress report, 1 April-30 June 1981

Energy Technology Data Exchange (ETDEWEB)

None

1981-01-01

This report describes the technical accomplishments during the quarter ending June 1981, on the commercial nuclear waste management programs under the direction of the Office of Nuclear Waste Isolation (ONWI). The ONWI program is organized into 8 tasks entitled: systems, waste package, site, repository, regulatory and institutional, test facilities and excavations, land acquisition, and program management. Principal investigators in each of these areas have submitted summaries of quarterly highlights for inclusion in this report. Separate abstracts have been prepared for 5 of these tasks for inclusion in the Energy Data Base. (DMC)

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-04-01

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

Technical Cybersecurity Controls for Nuclear Facilities

International Nuclear Information System (INIS)

Oh, Jinseok; Ryou, Jaecheol; Kim, Youngmi; Jeong, Choonghei

2014-01-01

To strengthen cybersecurity for nuclear facilities, many countries take a regulatory approach. For example, US Government issued several regulations . Title 10, of the Code of Federal Regulations, Section 73.54, 'Protection of Digital Computer and Communication Systems and Networks (10 CFR 73.54) for cybersecurity requirements and Regulatory Guide 5.71 (RG. 5.71) for cybersecurity guidance and so on. In the case of Korea, Korean Government issued '8.22 Cybersecurity of I and C systems (KINS/RG-NO8.22). In particular, Reg. 5.71 provides a list of security controls to address the potential cyber risks to a nuclear facilities. Implementing and adopting security controls, we can improve the level of cybersecurity for nuclear facilities. RG 5.71 follows the recommendation of NIST SP 800-53. NIST standard provides security controls for IT systems. And NRC staff tailored the controls in NIST standards to unique environments of nuclear facilities. In this paper, we are going to analysis and compare NRC RG 5.71 and NIST SP800-53, in particular, for technical security controls. If RG 5.71 omits the specific security control that is included in SP800-53, we would review that omitting is adequate or not. If RG 5.71 includes the specific security control that is not included in SP800-53, we would also review the rationale. And we are going to some security controls to strengthen cybersecurity of nuclear facilities. In this paper, we compared and analyzed of two regulation in technical security controls. RG 5.71 that is based on NIST standard provides well-understood security controls for nuclear facility. But some omitting from NIST standard can threaten security state of nuclear facility

Technical Cybersecurity Controls for Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Oh, Jinseok; Ryou, Jaecheol [Chungnam National Univ., Daejeon (Korea, Republic of); Kim, Youngmi; Jeong, Choonghei [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2014-05-15

To strengthen cybersecurity for nuclear facilities, many countries take a regulatory approach. For example, US Government issued several regulations . Title 10, of the Code of Federal Regulations, Section 73.54, 'Protection of Digital Computer and Communication Systems and Networks (10 CFR 73.54) for cybersecurity requirements and Regulatory Guide 5.71 (RG. 5.71) for cybersecurity guidance and so on. In the case of Korea, Korean Government issued '8.22 Cybersecurity of I and C systems (KINS/RG-NO8.22). In particular, Reg. 5.71 provides a list of security controls to address the potential cyber risks to a nuclear facilities. Implementing and adopting security controls, we can improve the level of cybersecurity for nuclear facilities. RG 5.71 follows the recommendation of NIST SP 800-53. NIST standard provides security controls for IT systems. And NRC staff tailored the controls in NIST standards to unique environments of nuclear facilities. In this paper, we are going to analysis and compare NRC RG 5.71 and NIST SP800-53, in particular, for technical security controls. If RG 5.71 omits the specific security control that is included in SP800-53, we would review that omitting is adequate or not. If RG 5.71 includes the specific security control that is not included in SP800-53, we would also review the rationale. And we are going to some security controls to strengthen cybersecurity of nuclear facilities. In this paper, we compared and analyzed of two regulation in technical security controls. RG 5.71 that is based on NIST standard provides well-understood security controls for nuclear facility. But some omitting from NIST standard can threaten security state of nuclear facility.

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

International Nuclear Information System (INIS)

1995-10-01

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

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

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.

Trend chart: wind power. Third quarter 2015

International Nuclear Information System (INIS)

Reynaud, Didier

2015-11-01

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

Trend chart: wind power. Forth quarter 2016

International Nuclear Information System (INIS)

Coltier, Yves

2017-02-01

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

Trend chart: wind power. First quarter 2016

International Nuclear Information System (INIS)

Reynaud, Didier

2016-05-01

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

Trend chart: wind power. Third quarter 2016

International Nuclear Information System (INIS)

Reynaud, Didier

2016-11-01

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

Trend chart: wind power. Second quarter 2016

International Nuclear Information System (INIS)

Reynaud, Didier

2016-08-01

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

Trend chart: wind power. First quarter 2017

International Nuclear Information System (INIS)

2017-05-01

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

Trend chart: wind power. Forth quarter 2015

International Nuclear Information System (INIS)

Reynaud, Didier

2016-02-01

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

Quarterly environmental data summary for fourth quarter 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

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

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)

Trend chart: wind power. Second quarter 2017

International Nuclear Information System (INIS)

2017-08-01

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

Trend chart: wind power. Fourth quarter 2017

International Nuclear Information System (INIS)

Moreau, Sylvain

2018-02-01

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

Trend chart: wind power. Third quarter 2017

International Nuclear Information System (INIS)

2017-11-01

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

Technical specifications for the Oak Ridge Critical Experiments Facility

International Nuclear Information System (INIS)

Stinnett, R.M.

1986-01-01

These Technical Specifications for the Oak Ridge Critical Experiments Facility (CEF) delineate limiting conditions of operation for the facility. The CEF is used primarily for testing the High Flux Isotope Reactor (HFIR) fuel assemblies. Specifically, the Criticality Testing Unit, Liquid (CTUL), located in the CEF, is used for the HFIR fuel assembly test. The test is performed to satisfy the surveillance requirements of the HFIR Technical Specifications. The test is used to determine the water-submerged shutdown margin for each fuel assembly. 11 refs

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).

Technical requirement of experiments and facilities for fusion nuclear technology

International Nuclear Information System (INIS)

Abdou, M.; Tillak, M.; Gierszwski, P.; Grover, J.; Puigh, R.; Sze, D.K.; Berwald, D.

1986-06-01

The technical issues and requirements of experiments and facilities for fusion nuclear technology (FNT) have been investigated. The nuclear subsystems addressed are: a) blanket, b) radiation shield, c) tritium processing system, and d) plasma interactive components. Emphasis has been placed on the important and complex development problems of the blanket. A technical planning process for FNT has been developed and applied, including four major elements: 1) characterization of issues, 2) quantification of testing requirements, 3) evaluation of facilities, and 4) development of a test plan to identify the role, timing, characteristics and costs of major experiments and facilities

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.

Branch technical position for performance assessment of low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Campbell, A.C.; Abramson, L.; Byrne, R.M.

1994-01-01

The U.S. Nuclear Regulatory Commission has developed a Draft Branch Technical Position on Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. The draft technical position addresses important issues in performance assessment modeling and provides a framework and technical basis for conducting and evaluating performance assessments in a disposal facility license application. The technical position also addresses specific technical policy issues and augments existing NRC guidance pertaining to LLW performance assessment

Physical protection of nuclear facilities. Quarterly progress report, July--September 1978. [PWR; BWR

Energy Technology Data Exchange (ETDEWEB)

Chapman, L.D. (ed.)

1979-01-01

Major activities during the fourth quarter of FY78 included (1) the vital area analysis of operational reactors and characterization of the Standardized Nuclear Unit Power Plant System (SNUPPS), (2) the algorithm development of a new pathfinding computer code, (3) the completion of contractor-supported work for the component generic data base, (4) the refinement of tests related to human parameters modeling, and (5) the addition of improvements to and demonstration of the Safeguards Automated Facility Evaluation (SAFE), Safeguards Network Analysis Procedure (SNAP), and Fixed-Site Neutralization Model (FSNM) methodologies.

Results For The Third Quarter Calendar Year 2016 Tank 50H Salt Solution Sample

Energy Technology Data Exchange (ETDEWEB)

Crawford, C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-10-13

In this memorandum, the chemical and radionuclide contaminant results from the Third Quarter Calendar Year 2016 (CY16) sample of Tank 50H salt solution are presented in tabulated form. The Third Quarter CY16 Tank 50H samples (a 200 mL sample obtained 6” below the surface (HTF-5-16-63) and a 1 L sample obtained 66” from the tank bottom (HTF-50-16-64)) were obtained on July 14, 2016 and received at Savannah River National Laboratory (SRNL) on the same day. Prior to obtaining the samples from Tank 50H, a single pump was run at least 4.4 hours, and the samples were pulled immediately after pump shut down. The information from this characterization will be used by Defense Waste Processing Facility (DWPF) & Saltstone Facility Engineering for the transfer of aqueous waste from Tank 50H to the Saltstone Production Facility, where the waste will be treated and disposed of in the Saltstone Disposal Facility. This memorandum compares results, where applicable, to Saltstone Waste Acceptance Criteria (WAC) limits and targets. Data pertaining to the regulatory limits for Resource Conservation and Recovery Act (RCRA) metals will be documented at a later time per the Task Technical and Quality Assurance Plan (TTQAP) for the Tank 50H saltstone task. The chemical and radionuclide contaminant results from the characterization of the Third Quarter CY16 sampling of Tank 50H were requested by Savannah River Remediation (SRR) personnel and details of the testing are presented in the SRNL TTQAP.

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

International Nuclear Information System (INIS)

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

1993-03-01

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

Integrated Data Collection Analysis (IDCA) Program — Quarterly Review Meeting

Energy Technology Data Exchange (ETDEWEB)

Sandstrom, Mary M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Brown, Geoffrey W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Warner, Kirstin F. [Naval Surface Warfare Center (IHD-NSWC), Indian Head, MD (United States). Indian Head Division; Sorensen, Daniel N. [Naval Surface Warfare Center (IHD-NSWC), Indian Head, MD (United States). Indian Head Division; Remmers, Daniel L. [Naval Surface Warfare Center (IHD-NSWC), Indian Head, MD (United States). Indian Head Division; Shelley, Timothy J. [Air Force Research Lab. (AFRL/RXQF), Tyndall AFB, FL (United States); Reyes, Jose A. [Applied Research Associates, Inc., Tyndall AFB, FL (United States); Phillips, Jason J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hsu, Peter C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Reynolds, John G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2011-12-05

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

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

International Nuclear Information System (INIS)

Moreau, Sylvain

2017-11-01

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

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

International Nuclear Information System (INIS)

2017-08-01

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

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

International Nuclear Information System (INIS)

Moreau, Sylvain

2018-02-01

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

Designing and constructing/installing technical security countermeasures (TSCM) into supersensitive facilities

International Nuclear Information System (INIS)

Davis, D.L.

1988-01-01

The design and construction of supersensitive facilities and the installation of systems secure from technical surveillance and sabotage penetration involve ''TSCM'' in the broad sense of technical ''security'' countermeasures. When the technical threat was at a lower level of intensity and sophistication, it was common practice to defer TSCM to the future facility occupant. However, the New Moscow Embassy experience has proven this course of action subject to peril. Although primary concern with the embassy was audio surveillance, elsewhere there are other threats of equal or greater concern, e.g., technical implants may be used to monitor readiness status or interfere with the operation of C3I and weapons systems. Present and future technical penetration threats stretch the imagination. The Soviets have committed substantial hard scientific resources to a broad range of technical intelligence, even including applications or parapsychology. Countering these threats involves continuous TSCM precautions from initial planning to completion. Designs and construction/installation techniques must facilitate technical inspections and preclude the broadest range of known and suspected technical penetration efforts

Designing and constructing/installing technical security countermeasures (TSCM) into supersensitive facilities

Energy Technology Data Exchange (ETDEWEB)

Davis, D.L.

1988-01-01

The design and construction of supersensitive facilities and the installation of systems secure from technical surveillance and sabotage penetration involve ''TSCM'' in the broad sense of technical ''security'' countermeasures. When the technical threat was at a lower level of intensity and sophistication, it was common practice to defer TSCM to the future facility occupant. However, the New Moscow Embassy experience has proven this course of action subject to peril. Although primary concern with the embassy was audio surveillance, elsewhere there are other threats of equal or greater concern, e.g., technical implants may be used to monitor readiness status or interfere with the operation of C3I and weapons systems. Present and future technical penetration threats stretch the imagination. The Soviets have committed substantial hard scientific resources to a broad range of technical intelligence, even including applications or parapsychology. Countering these threats involves continuous TSCM precautions from initial planning to completion. Designs and construction/installation techniques must facilitate technical inspections and preclude the broadest range of known and suspected technical penetration efforts.

the effects of unavailability of technical storage facilities

African Journals Online (AJOL)

unavailability of the technical storage facilities to the marketing of fruits and vegetables for economic ... vegetables are important profitable small-scale juice enterprises (Thomson,. 1990). ..... Knott's handbook for vegetables growers. 2nd ed.

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

International Nuclear Information System (INIS)

2017-05-01

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

Technical Safety Requirements for the Gamma Irradiation Facility (GIF)

CERN Document Server

Mahn, J A E M J G

2003-01-01

This document provides the Technical Safety Requirements (TSR) for the Sandia National Laboratories Gamma Irradiation Facility (GIF). The TSR is a compilation of requirements that define the conditions, the safe boundaries, and the administrative controls necessary to ensure the safe operation of a nuclear facility and to reduce the potential risk to the public and facility workers from uncontrolled releases of radioactive or other hazardous materials. These requirements constitute an agreement between DOE and Sandia National Laboratories management regarding the safe operation of the Gamma Irradiation Facility.

F/H effluent treatment facility. Technical data summary

International Nuclear Information System (INIS)

Ryan, J.P.; Stimson, R.E.

1984-12-01

This document provides the technical basis for the design of the facility. Some of the sections are described with options to permit simplification of the process, depending on the effluent quality criteria that the facility will have to meet. Each part of the F/HETF process is reviewed with respect to decontamination and concentration efficiency, operability, additional waste generation, energy efficiency, and compatability with the rest of the process

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

International Nuclear Information System (INIS)

1995-05-01

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

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.

Functional criteria for emergency response facilities. Technical report (final)

International Nuclear Information System (INIS)

1981-02-01

This report describes the facilities and systems to be used by nuclear power plant licensees to improve responses to emergency situations. The facilities include the Technical Support Center (TSC), Onsite Operational Support Center (OSC), and Nearsite Emergency Operations Facility (EOF), as well as a brief discussion of the emergency response function of the control room. The data systems described are the Safety Parameter Display System (SPDS) and Nuclear Data Link (NDL). Together, these facilities and systems make up the total Emergency Response Facilities (ERFs). Licensees should follow the guidance provided both in this report and in NUREG-0654 (FEMA-REP-1), Revision 1, for design and implementation of the ERFs

Technical concept for a Greater Confinement Disposal test facility

International Nuclear Information System (INIS)

Hunter, P.H.

1982-01-01

For the past two years, Ford, Bacon and Davis has been performing technical services for the Department of Energy at the Nevada Test Site in specific development of defense low-level waste management concepts for greater confinement disposal concept with particular application to arid sites. The investigations have included the development of Criteria for Greater Confinement Disposal, NVO-234, which was published in May of 1981 and the draft of the technical concept for Greater Confinement Disposal, with the latest draft published in November 1981. The final draft of the technical concept and design specifications are expected to be published imminently. The document is prerequisite to the actual construction and implementation of the demonstration facility this fiscal year. The GCD Criteria Document, NVO-234 is considered to contain information complimentary and compatible with that being developed for the reserved section 10 CFR 61.51b of the NRCs proposed licensing rule for low level waste disposal facilities

Joint ACE ground penetrating radar antenna test facility at the Technical University of Denmark

DEFF Research Database (Denmark)

Lenler-Eriksen, Hans-Rudolph; Meincke, Peter; Sarri, A.

2005-01-01

A ground penetrating radar (GPR) antenna test facility, established within the ACE network at the Technical University of Denmark (DTU), is described. Examples of results from the facility obtained from measurements of eight different GPR antennas are presented.......A ground penetrating radar (GPR) antenna test facility, established within the ACE network at the Technical University of Denmark (DTU), is described. Examples of results from the facility obtained from measurements of eight different GPR antennas are presented....

Surface Fire Hazards Analysis Technical Report-Constructor Facilities

International Nuclear Information System (INIS)

Flye, R.E.

2000-01-01

The purpose of this Fire Hazards Analysis Technical Report (hereinafter referred to as Technical Report) is to assess the risk from fire within individual fire areas to ascertain whether the U.S. Department of Energy (DOE) fire safety objectives are met. The objectives identified in DOE Order 420.1, Change 2, Facility Safety, Section 4.2, establish requirements for a comprehensive fire and related hazards protection program for facilities sufficient to minimize the potential for: The occurrence of a fire or related event; A fire that causes an unacceptable on-site or off-site release of hazardous or radiological material that will threaten the health and safety of employees, the public, or the environment; Vital DOE programs suffering unacceptable interruptions as a result of fire and related hazards; Property losses from a fire and related events exceeding defined limits established by DOE; and Critical process controls and safety class systems being damaged as a result of a fire and related events

M-Area and Metallurgical Laboratory Hazardous Waste Management Facilities Groundwater Monitoring and Corrective-Action Report, First and Second Quarters 1999, Volume III

International Nuclear Information System (INIS)

Chase, J.

1999-01-01

This report describes the groundwater monitoring and corrective-action program at the M-Area Hazardous Waste Management Facility (HWMF) and the Metallurgical Laboratory (Met Lab) HWMF at the Savannah River Site (SRS) during the first and second quarters 1999

Technical viability and development needs for waste forms and facilities

Energy Technology Data Exchange (ETDEWEB)

Pegg, I.; Gould, T.

1996-05-01

The objective of this breakout session was to provide a forum to discuss technical issues relating to plutonium-bearing waste forms and their disposal facilities. Specific topics for discussion included the technical viability and development needs associated with the waste forms and/or disposal facilities. The expected end result of the session was an in-depth (so far as the limited time would allow) discussion of key issues by the session participants. The session chairs expressed allowance for, and encouragement of, alternative points of view, as well as encouragement for discussion of any relevant topics not addressed in the paper presentations. It was not the intent of this session to recommend or advocate any one technology over another.

Trend chart: photovoltaic solar energy. Second quarter 2016

International Nuclear Information System (INIS)

Reynaud, Didier

2016-08-01

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

Trend chart: photovoltaic solar energy. First quarter 2016

International Nuclear Information System (INIS)

Reynaud, Didier

2016-05-01

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

Technical safety requirements for the Annular Core Research Reactor Facility (ACRRF)

International Nuclear Information System (INIS)

Boldt, K.R.; Morris, F.M.; Talley, D.G.; McCrory, F.M.

1998-01-01

The Technical Safety Requirements (TSR) document is prepared and issued in compliance with DOE Order 5480.22, Technical Safety Requirements. The bases for the TSR are established in the ACRRF Safety Analysis Report issued in compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports. The TSR identifies the operational conditions, boundaries, and administrative controls for the safe operation of the facility

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

International Nuclear Information System (INIS)

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

1997-01-01

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

Process Technical Basis Documentation Diagram for a solid-waste processing facility

International Nuclear Information System (INIS)

Benar, C.J.; Petersen, C.A.

1994-02-01

The Process Technical Basis Documentation Diagram is for a solid-waste processing facility that could be designed to treat, package, and certify contact-handled mixed low-level waste for permanent disposal. The treatment processes include stabilization using cementitious materials and immobilization using a polymer material. The Diagram identifies several engineering/demonstration activities that would confirm the process selection and process design. An independent peer review was conducted at the request of Westinghouse Hanford Company to determine the technical adequacy of the technical approach for waste form development. The peer review panel provided comments and identified documents that it felt were needed in the Diagram as precedence for Title I design. The Diagram is a visual tool to identify traceable documentation of key activities, including those documents suggested by the peer review, and to show how they relate to each other. The Diagram is divided into three sections: (1) the Facility section, which contains documents pertaining to the facility design, (2) the Process Demonstration section, which contains documents pertaining to the process engineering/demonstration work, and 3) the Regulatory section, which contains documents describing the compliance strategy for each acceptance requirement for each feed type, and how this strategy will be implemented

Emergency response facility technical data system of Taiwan Power Company

International Nuclear Information System (INIS)

Lin, E.; Liang, T.M.

1987-01-01

Taiwan Power Company (Taipower) has developed its emergency response facility program since 1981. This program is integrated with the following activities to enhance the emergency response capability of nuclear power plants: (1) survey of the plant instrumentation based on the requirements of R.G. 1.97; (2) improvement of plant specific emergency operating procedures based on the emergency response guidelines developed by the Owners group; (3) implementation of the detailed control room design review with the consideration of human engineering and task analysis; and (4) organization, staff and communication of emergency planning of nuclear power plant. The emergency response facility programs of Taipower are implemented in Chinshan (GE BWR4/MARK I), Kuosheng (GE BWR6/MARK III) and Maanshan (W PWR). The major items included in each program are: (1) to establish new buildings for On-Site Technical Support Center, Near-Site Emergency Operation Facility; (2) to establish an Emergency Executive Center at Taipower headquarters; (3) to establish the communication network between control room and emergency response facilities; and (4) to install a dedicated Emergency Response Facility Technical Data System (ERFTDS) for each plant. The ERFTDS provides the functions of data acquisition, data processing, data storage and display in meeting with the requirements of NUREG 0696. The ERFTDS is designed with plant specific requirements. These specific requirements are expected to be useful not only for the emergency condition but also for normal operation conditions

Preliminary technical data summary defense waste processing facility stage 2

International Nuclear Information System (INIS)

1980-12-01

This Preliminary Technical Data Summary presents the technical basis for design of Stage 2 of the Staged Defense Waste Processing Facility (DWPF). Process changes incorporated in the staged DWPF relative to the Alternative DWPF described in PTDS No. 3 (DPSTD-77-13-3) are the result of ongoing research and development and are aimed at reducing initial capital investment and developing a process to efficiently immobilize the radionuclides in Savannah River Plant (SRP) high-level liquid waste. The radionuclides in SRP waste are present in sludge that has settled to the bottom of waste storage tanks and in crystallized salt and salt solution (supernate). Stage 1 of the DWPF receives washed, aluminum dissolved sludge from the waste tank farms and immobilizes it in a borosilicate glass matrix. The supernate is retained in the waste tank farms until completion of Stage 2 of the DWPF at which time it is filtered and decontaminated by ion exchange in the Stage 2 facility. The decontaminated supernate is concentrated by evaporation and mixed with cement for burial. The radioactivity removed from the supernate is fixed in borosilicate glass along with the sludge. This document gives flowsheets, material and curie balances, material and curie balance bases, and other technical data for design of Stage 2 of the DWPF. Stage 1 technical data are presented in DPSTD-80-38

Paul Scherrer Institute Scientific and Technical Report 2000. Volume VI: Large Research Facilities

International Nuclear Information System (INIS)

Foroughi, Fereydoun; Bercher, Renate; Buechli, Carmen; Zumkeller, Lotty

2001-01-01

The PSI Department Large Research Facilities (GFA) joins the efforts to provide an excellent research environment to Swiss and foreign research groups on the experimental facilities driven by our high intensity proton accelerator complex. Its divisions care for the running, maintenance and enhancement of the accelerator complex, the primary proton beamlines, the targets and the secondary beams as well as the neutron spallation source SINQ. The division for technical support and coordination provides for technical support to the research facility complementary to the basic logistic available from the department for logistics and marketing. Besides running the facilities, the staff of the department is also involved in theoretical and experimental research projects. Some of them address basic scientific questions mainly concerning the properties of micro- or nanostructured materials: experiments as well as large scale computer simulations of molecular dynamics were performed to investigate nonclassical materials properties. Others are related to improvements or extensions of the capabilities of our facilities. We also report on intriguing results from applications of the neutron capture radiography, the prompt gamma activation method and the isotope production facility at SINQ

Paul Scherrer Institute Scientific and Technical Report 2000. Volume VI: Large Research Facilities

Energy Technology Data Exchange (ETDEWEB)

Foroughi, Fereydoun; Bercher, Renate; Buechli, Carmen; Zumkeller, Lotty [eds.

2001-07-01

The PSI Department Large Research Facilities (GFA) joins the efforts to provide an excellent research environment to Swiss and foreign research groups on the experimental facilities driven by our high intensity proton accelerator complex. Its divisions care for the running, maintenance and enhancement of the accelerator complex, the primary proton beamlines, the targets and the secondary beams as well as the neutron spallation source SINQ. The division for technical support and coordination provides for technical support to the research facility complementary to the basic logistic available from the department for logistics and marketing. Besides running the facilities, the staff of the department is also involved in theoretical and experimental research projects. Some of them address basic scientific questions mainly concerning the properties of micro- or nanostructured materials: experiments as well as large scale computer simulations of molecular dynamics were performed to investigate nonclassical materials properties. Others are related to improvements or extensions of the capabilities of our facilities. We also report on intriguing results from applications of the neutron capture radiography, the prompt gamma activation method and the isotope production facility at SINQ.

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.

Quarterly report on Defense Nuclear Facilities Safety Board Recommendation 90-7 for the period ending December 31, 1991

International Nuclear Information System (INIS)

Cash, R.J.; Dukelow, G.T.; Atwood, J.M.

1992-01-01

This quarterly report provides a status of the activities underway at the Hanford Site on the ferrocyanide safety issues as requested by the Defense Nuclear Facilities Safety Board (DNFSB) in their Recommendation 90-7 (FR 1990). In March 1991, an DNFSB Implementation Plan (Cash 1991a) was prepared and sent to the DNFSB responding to the six parts of Recommendation 90-7. All of the activities in the DNFSB Implementation Plan are underway and the status of each is described

Trend chart: biogas for electricity production. Fourth quarter 2017

International Nuclear Information System (INIS)

Moreau, Sylvain

2018-02-01

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

Trend chart: biogas for electricity production. Third quarter 2017

International Nuclear Information System (INIS)

Moreau, Sylvain

2017-11-01

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

Trend chart: biogas for electricity production. Second quarter 2017

International Nuclear Information System (INIS)

2017-08-01

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

Occupants' satisfaction on building maintenance of government quarters

Science.gov (United States)

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

2017-10-01

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

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

International Nuclear Information System (INIS)

1995-01-01

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

Trend chart: biogas for electricity production. First quarter 2017

International Nuclear Information System (INIS)

2017-05-01

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

Decontamination Systems Information and Research Program: Quarterly report, July--September 1994

International Nuclear Information System (INIS)

1994-11-01

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'' (DOE Instrument No.: DE-FC21-92MC29467). 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 eighth Quarterly Technical Progress Report for the Agreement. This report reflects the progress and/or efforts performed on the 16 technical projects encompassed by the Agreement for the period of July 1 through September 30, 1994. These projects focus on the following: Bio-remediation of organic compounds, heavy metals, and radionuclides; miscellaneous remediation technologies; instrumentation; and technology assessments

A monitored retrievable storage facility: Technical background information

International Nuclear Information System (INIS)

1991-07-01

The US government is seeking a site for a monitored retrievable storage facility (MRS). Employing proven technologies used in this country and abroad, the MRS will be an integral part of the federal system for safe and permanent disposal of the nation's high-level radioactive wastes. The MRS will accept shipments of spent fuel from commercial nuclear power plants, temporarily store the spent fuel above ground, and stage shipments of it to a geologic repository for permanent disposal. The law authorizing the MRS provides an opportunity for a state or an Indian tribe to volunteer to host the MRS. The law establishes the Office of the Nuclear Waste Negotiator, who is to seek a state or an Indian tribe willing to host an MRS at a technically-qualified site on reasonable terms, and is to negotiate a proposed agreement specifying the terms and conditions under which the MRS would be developed and operated at that site. This agreement can ensure that the MRS is acceptable to -- and benefits -- the host community. The proposed agreement must be submitted to Congress and enacted into law to become effective. This technical background information presents an overview of various aspects of a monitored retrievable storage facility, including the process by which it will be developed

Technical Safety Requirements for the Waste Storage Facilities May 2014

Energy Technology Data Exchange (ETDEWEB)

Laycak, D. T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2014-04-16

This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

Technical Safety Requirements for the Waste Storage Facilities May 2014

International Nuclear Information System (INIS)

Laycak, D. T.

2014-01-01

This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

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.)

Review of Sodium and Plutonium related Technical Standards in Trans-Uranium Fuel Fabrication Facilities

Energy Technology Data Exchange (ETDEWEB)

Jang, Misuk; Jeon, Jong Seon; Kang, Hyun Sik; Kim, Seoung Rae [NESS, Daejeon (Korea, Republic of)

2016-10-15

In this paper, we would introduce and review technical standards related to sodium fire and plutonium criticality safety. This paper may be helpful to identify considerations in the development of equipment, standards, and etc., to meet the safety requirements in the design, construction and operating of TFFF, KAPF and SFR. The feasibility and conceptual designs are being examined on related facilities, for example, TRU Fuel Fabrication Facilities (TFFF), Korea Advanced Pyro-process Facility (KAPF), and Sodium Cooled Fast Reactor (SFR), in Korea. However, the safety concerns of these facilities have been controversial in part because of the Sodium fire accident and Plutonium related radiation safety caused by transport and handling accident. Thus, many researches have been performed to ensure safety and various documents including safety requirements have been developed. In separating and reducing the long-lived radioactive transuranic(TRU) in the spent nuclear fuel, reusing as the potential energy of uranium fuel resources and reducing the high level wastes, TFFF would be receiving the attention of many people. Thus, people would wonder whether compliance with technical standards that ensures safety. For new facility design, one of the important tasks is to review of technical standards, especially for sodium and Plutonium because of water related highly reactive characteristics and criticality hazard respectively. We have introduced and reviewed two important technical standards for TFFF, which are sodium fire and plutonium criticality safety, in this paper. This paper would provide a brief guidance, about how to start and what is important, to people who are responsible for the initial design to operation of TFFF.

Review of Sodium and Plutonium related Technical Standards in Trans-Uranium Fuel Fabrication Facilities

International Nuclear Information System (INIS)

Jang, Misuk; Jeon, Jong Seon; Kang, Hyun Sik; Kim, Seoung Rae

2016-01-01

In this paper, we would introduce and review technical standards related to sodium fire and plutonium criticality safety. This paper may be helpful to identify considerations in the development of equipment, standards, and etc., to meet the safety requirements in the design, construction and operating of TFFF, KAPF and SFR. The feasibility and conceptual designs are being examined on related facilities, for example, TRU Fuel Fabrication Facilities (TFFF), Korea Advanced Pyro-process Facility (KAPF), and Sodium Cooled Fast Reactor (SFR), in Korea. However, the safety concerns of these facilities have been controversial in part because of the Sodium fire accident and Plutonium related radiation safety caused by transport and handling accident. Thus, many researches have been performed to ensure safety and various documents including safety requirements have been developed. In separating and reducing the long-lived radioactive transuranic(TRU) in the spent nuclear fuel, reusing as the potential energy of uranium fuel resources and reducing the high level wastes, TFFF would be receiving the attention of many people. Thus, people would wonder whether compliance with technical standards that ensures safety. For new facility design, one of the important tasks is to review of technical standards, especially for sodium and Plutonium because of water related highly reactive characteristics and criticality hazard respectively. We have introduced and reviewed two important technical standards for TFFF, which are sodium fire and plutonium criticality safety, in this paper. This paper would provide a brief guidance, about how to start and what is important, to people who are responsible for the initial design to operation of TFFF

Technical critique on radiation test facilities for the CTR surface and materials program

International Nuclear Information System (INIS)

Persiani, P.J.

1975-02-01

Major radiation test facilities will be necessary in the near-term (5 years) and long-term (greater than 10 years) future for the timely development and understanding of fusion confinement systems and of prototype fusion power reactors. The study includes the technical justifications and requirements for CTR Neutron and Plasma Radiation Test Facilities. The initial technical critique covers the feasibility and design problems: in upgrading the performance of the accelerator-rotating (solid TiT) target systems, and in transforming the accelerator-supersonic jet target concept into a radiation testing facility. A scoping assessment on the potential of a pulsed high-beta plasma device (dense plasma focus) is introduced to explore plasma concepts as near-term neutron and plasma radiation sources for the CTR Surface and Materials Program. (U.S.)

Lawrence Livermore National Laboratory safeguards and security quarterly progress report to the US Department of Energy: Quarter ending September 30, 1993

Energy Technology Data Exchange (ETDEWEB)

Ruhter, W.D.; Strait, R.S.; Mansur, D.L.; Davis, G.

1993-10-01

The Lawrence Livermore National Laboratory (LLNL) carries out safeguards and security activities for the Department of Energy (DOE), Office of Safeguards and Security (OSS), as well as other organizations, both within and outside the DOE. This document summarizes the activities conducted for the OSS during the fourth quarter of Fiscal Year 1993 (July through September, 1993). The nature and scope of the activities carried out for OSS at LLNL require a broad base of technical expertise. To assure projects are staffed and executed effectively, projects are conducted by the organization at LLNL best able to supply the needed technical expertise. These projects are developed and managed by senior program managers. Institutional oversight and coordination is provided through the LLNL Deputy Director`s office. At present, the Laboratory is supporting OSS in five areas: Safeguards Technology, Safeguard System Studies, Computer Security, DOE Automated Physical Security and DOE Automated Visitor Access Control System. The remainder of this report describes the activities in each of these five areas. The information provided includes an introduction which briefly describes the activity, summary of major accomplishments, task descriptions with quarterly progress, summaries of milestones and deliverables and publications published this quarter.

Performance of simulated flexible integrated gasification polygeneration facilities. Part A: A technical-energetic assessment

NARCIS (Netherlands)

Meerman, J.C.; Ramírez Ramírez, C.A.; Turkenburg, W.C.; Faaij, A.P.C.

2011-01-01

This article investigates technical possibilities and performances of flexible integrated gasification polygeneration (IG-PG) facilities equipped with CO2 capture for the near future. These facilities can produce electricity during peak hours, while switching to the production of chemicals during

Yucca Mountain Site Characterization Project Technical Data Catalog

International Nuclear Information System (INIS)

1992-01-01

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. Each new publication of the Technical Data Catalog supersedes the previous edition

Yucca Mountain Site Characterization Project technical data catalog

International Nuclear Information System (INIS)

1992-01-01

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. Each new publication of the Technical Data Catalog supersedes the previous edition

Technical on the TAB of air handling system in IMEF facility

International Nuclear Information System (INIS)

Oh, Yon Woo; Baik, S. Y.; Kim, S. D.; Lee, B. J.

2002-08-01

A T.A.B(Testing, Adjusting and Balancing) technique, the basic technique of air handling facility, is one of the essential technical items which workers in charge of operation of facilities have to acquire. Especially, through scientific and reasonable inspective procedures, the reduction of energy and guarantee of designed skill have become influential important problems in our time rather than in the past days. Entrepreneurs have required more thorough verify of performances and procedure of test in order to raise the investment efficiency and reduce expenditure. For that reason, I hope that cooperator acquire objective and substantial knowledges about air handling facility so that they are helped from them

Lawrence Livermore National Laboratory safeguards and security quarterly progress report to the U.S. Department of Energy. Quarter ending December 31, 1996

Energy Technology Data Exchange (ETDEWEB)

Davis, G.; Mansur, D.L.; Ruhter, W.D.; Strauch, M.S.

1997-01-01

The Lawrence Livermore National Laboratory (LLNL) carries out safeguards and security activities for the Department of Energy (DOE), Office of Safeguards and Security (OSS), as well as other organizations, both within and outside the DOE. This document summarizes the activities conducted for the OSS during the First Quarter of Fiscal Year 1997 (October through December, 1996). The nature and scope of the activities carried out for OSS at LLNL require a broad base of technical expertise. To assure projects are staffed and executed effectively, projects are conducted by the organization at LLNL best able to supply the needed technical expertise. These projects are developed and managed by senior program managers. Institutional oversight and coordination is provided through the LLNL Deputy Director`s office. At present, the Laboratory is supporting OSS in four areas: (1) safeguards technology; (2) safeguards and material accountability; (3) computer security--distributed systems; and (4) physical and personnel security support. The remainder of this report describes the activities in each of these four areas. The information provided includes an introduction which briefly describes the activity, summary of major accomplishments, task descriptions with quarterly progress, summaries of milestones and deliverables and publications published this quarter.

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

Preliminary technical data summary for the Defense Waste Processing Facility, Stage 1

International Nuclear Information System (INIS)

1980-09-01

This Preliminary Technical Data Summary presents the technical basis for design of Stage 1 of the Staged Defense Waste Processing Facility (DWPF), a process to efficiently immobilize the radionuclides in Savannah River Plant (SRP) high-level liquid waste. The radionuclides in SRP waste are present in sludge that has settled to the bottom of waste storage tanks and in crystallized salt and salt solution (supernate). Stage 1 of the DWPF receives washed, aluminum dissolved sludge from the waste tank farms and immobilizes it in a borosilicate glass matrix. The supernate is retained in the waste tank farms until completion of Stage 2 of the DWPF at which time it filtered and decontaminated by ion exchange in the Stage 2 facility. The decontaminated supernate is concentrated by evaporation and mixed with cement for burial. The radioactivity removed from the supernate is fixed in borosilicate glass along with the sludge. This document gives flowsheets, material, and curie balances, material and curie balance bases, and other technical data for design of the Stage 1 DWPF

Independent technical review of Savannah River Site Defense Waste Processing Facility technical issues

International Nuclear Information System (INIS)

1992-07-01

The Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) will vitrify high-level radioactive waste that is presently stored as liquid, salt-cake, and sludge in 51 waste-storage tanks. Construction of the DWPF began in 1984, and the Westinghouse Savannah Company (WSRC) considers the plant to be 100% turned over from construction and 91% complete. Cold-chemical runs are scheduled to begin in November 1992, and hot start up is projected for June 1994. It is estimated that the plant lifetime must exceed 15 years to complete the vitrification of the current, high-level tank waste. In a memo to the Assistant Secretary for Defense Programs (DP-1), the Assistant Secretary for Environmental Restoration and Waste management (EM-1) established the need for an Independent Technical Review (ITR), or the Red Team, to ''review process technology issues preventing start up of the DWPF.'' This report documents the findings of an Independent Technical Review (ITR) conducted by the Department of Energy (DOE), Office of Environmental Restoration and Waste Management (EM), at the request of the Assistant Secretary for Environmental Restoration and Waste Management, of specified aspects of Defense Waste Process Facility (DWPF) process technology. Information for the assessment was drawn from documents provided to the ITR Team by the Westinghouse Savannah River Company (WSRC), and presentations, discussions, interviews, and tours held at the Savannah River Site (SRS) during the weeks of February and March 9, 1992

Conceptual design of technical security systems for Russian nuclear facilities physical protection

International Nuclear Information System (INIS)

Izmailov, A.V.

1995-01-01

Conceptual design of technical security systems (TSS) used in the early stages of physical protection systems (PPS) design for Russia nuclear facilities is discussed. The importance of work carried out in the early stages was noted since the main design solutions are being made within this period (i.e. selection of a structure of TSS and its components). The methods of analysis and synthesis of TSS developed by ''Eleron'' (MINATOM of Russia) which take into account the specific conditions of Russian nuclear facilities and a scope of equipment available are described in the review. TSS effectiveness assessment is based on a probability theory and a simulation. The design procedure provides for a purposeful choice of TSS competitive options including a ''cost-benefit'' criterion and taking into account a prechosen list of design basis threats to be used for a particular facility. The attention is paid to a practical aspect of the methods application as well as to the bilateral Russian-American scientific and technical co-operation in the PPS design field

Technical issues in licensing low-level radioactive waste facilities

Energy Technology Data Exchange (ETDEWEB)

Junkert, R. [California Dept. of Health Services, CA (United States)

1993-03-01

The California Department of Health Service spent two years in the review of an application for a low-level radioactive waste disposal facility in California. During this review period a variety of technical issues had to be evaluated and resolved. One of the first issues was the applicability and use of NRC guidance documents for the development of LLW disposal facilities. Other technical issues that required intensive evaluations included surface water hydrology, seismic investigation, field and numerical analysis of the unsaturated zone, including a water infiltration test. Source term verification became an issue because of one specific isotope that comprised more than 90% of the curies projected for disposal during the operational period. The use of trench liners and the proposed monitoring of the unsaturated zone were reviewed by a highly select panel of experts to provide guidance on the need for liners and to ensure that the monitoring system was capable of monitoring sufficient representative areas for radionuclides in the soil, soil gas, and soil moisture. Finally, concerns about the quality of the preoperational environmental monitoring program, including data, sample collection procedures, laboratory analysis, data review and interpretation and duration of monitoring caused a significant delay in completing the licensing review.

Ministry of ordinance determining the technical standard concerning atomic energy facilities for power generation

International Nuclear Information System (INIS)

1985-01-01

The ministerial ordinance provides for the technical standards for the power generation of nuclear facilities; i.e., electric power facilities generating electricity with nuclear energy for motive power, according to the Electricity Enterprises Act. The contents are as follows: protection against fires, aseismatic design, radiation protective barriers, structural protection for sitings, reactor installation, safety measures, materials and structures, safety valves, pressure resistance tests, reactor core, radiation shields, reactor cooling, emergency core cooling system, facility equipment, alarm system, reactor control system, reactor control room, fuel storage facility, fuel handling facility, ventilation equipment, radioactive contamination prevention, radioactive waste management facility, reactor containment facility, and so on. (Kubozono, M.)

Quarterly report on program cost and schedule: Fourth quarter FY 1988

International Nuclear Information System (INIS)

1988-01-01

Major program milestones completed in the fourth quarter of FY 1988 include completed preliminary draft NWPAA Section 175 Impacts Report, completed Title I ESF design, completed site reclamation in Texas, distributed review draft of the Dry Cask Storage Study, completed draft and final FY 1990 OMB budget, issued FY 1987 Annual Report to Congress, issued four draft Environmental Field Activity Plans, issued draft Environmental Program Overview, and made grant payments to local governments under Section 116 of NWPA, as amended. Major accomplishments during the fourth quarter of FY 1988 are listed. The Water Appropriation Permit Application was filed with the Nevada State Engineer on July 21, 1988. Installation and checkout of the Prototype Engineered Barrier Test equipment in G-tunnel is continuing with an expected early September test initiation data. The Configuration Management Plan was sent to DOE/HQ for approval. The prototype facility for testing the horizontal waste package emplacement configuration was completed in the G-tunnel

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

International Nuclear Information System (INIS)

Chase, J.A.

1995-03-01

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

Results for the first quarter calendar year 2017 tank 50H salt solution sample

Energy Technology Data Exchange (ETDEWEB)

Crawford, C. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-04-12

In this memorandum, the chemical and radionuclide contaminant results from the First Quarter Calendar Year 2017 (CY17) sample of Tank 50H salt solution are presented in tabulated form. The First Quarter CY17 Tank 50H samples [a 200 mL sample obtained 6” below the surface (HTF-50-17-7) and a 1 L sample obtained 66” from the tank bottom (HTF-50-17-8)] were obtained on January 15, 2017 and received at Savannah River National Laboratory (SRNL) on January 16, 2017. Prior to obtaining the samples from Tank 50H, a single pump was run at least 4.4 hours and the samples were pulled immediately after pump shut down. All volatile organic analysis (VOA) and semi-volatile organic analysis (SVOA) were performed on the surface sample and all other analyses were performed on the variable depth sample. The information from this characterization will be used by Savannah River Remediation (SRR) for the transfer of aqueous waste from Tank 50H to the Saltstone Production Facility, where the waste will be treated and disposed of in the Saltstone Disposal Facility. This memorandum compares results, where applicable, to Saltstone Waste Acceptance Criteria (WAC) limits and targets. The chemical and radionuclide contaminant results from the characterization of the First Quarter CY17 sampling of Tank 50H were requested by SRR personnel and details of the testing are presented in the SRNL Task Technical and Quality Assurance Plan (TTQAP). This memorandum is part of Deliverable 2 from SRR request. Data pertaining to the regulatory limits for Resource Conservation and Recovery Act (RCRA) metals will be documented at a later time per the TTQAP for the Tank 50H saltstone task.

Cold Vacuum Drying (CVD) Facility Technical Safety Requirements

International Nuclear Information System (INIS)

KRAHN, D.E.

2000-01-01

The Technical Safety Requirements (TSRs) for the Cold Vacuum Drying Facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt of multi-canister overpacks (MCOs) containing spent nuclear fuel. removal of free water from the MCOs using the cold vacuum drying process, and inerting and testing of the MCOs before transport to the Canister Storage Building. Controls required for public safety, significant defense in depth, significant worker safety, and for maintaining radiological and toxicological consequences below risk evaluation guidelines are included

CSNI Technical Opinion Papers No. 15 - Ageing management of nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Nocture, Pierre; Daubard, Jean-Paul; Lhomme, Veronique; Martineau, Dominique; Blundell, Neil; Conte, Dorothee; Dobson, Martin; Gmal, Bernhard; Hiltz, Thomas; Ueda, Yoshinori

2012-01-01

Managing the ageing of fuel cycle facilities (FCFs) means, as for other nuclear installations, ensuring the availability of required safety functions throughout their service life while taking into account the changes that occur with time and use. This technical opinion paper identifies a set of good practices by benchmarking strategies and good practices on coping with physical ageing and obsolescence from the facility design stage until decommissioning. It should be of particular interest to nuclear safety regulators, fuel cycle facilities operators and fuel cycle researchers [fr

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.

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).

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.

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.

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)

Environmental licensing of nuclear facilities: compatibility of technical competencies

International Nuclear Information System (INIS)

Shu, J.; Paiva, R.L.C. de; Mezrahi, A.; Cardoso, E.M.; Aquino, W.P.; Deppe, A.L.; Menezes, R.M.; Prado, V.; Franco, N.M.F.L.; Nouailhetas, Y.; Xavier, A.M.

1996-01-01

The Brazilian Nuclear Energy Commission (CNEN) has the technical competency for diagnosing environmental radiological impacts, as well as evaluating the safety and requiring adequate control of the facilities which, due to their activities, represent a potential risk of radiological contamination for the environment. The institution is responsible for emission of radioprotection guidelines, controls and surveys in nuclear safety according to the country's regulations and international recommendations. The methodology to assure the limitation of radiation exposure is consequence from shared control over the nuclear activities, in special the nuclear facilities. According to the Federal Constitution of 1988, the nuclear activities must be under exclusive control of the Union in special related to the nuclear policies, economical, laboral and nuclear safety aspects, while the health and environmental controls of these activities are shared by the Federation, Union, States, Federal District and Counties. The controls related to specific aspects have to be harmonized in such a way to be optimized and effective. In this paper the results of compatibilization of nuclear legislation and environmental legislation are presented aiming to optimize the licensing of nuclear facilities. (author)

Technical, economic and institutional aspects of regional spent fuel storage facilities

International Nuclear Information System (INIS)

2005-11-01

A particular challenge facing countries with small nuclear programmes is the preparation for extended interim storage and then disposal of their spent nuclear fuel. The costs and complications of providing for away-from-reactor storage facilities and/or geological repositories for relatively small amounts of spent fuel may be prohibitively high, motivating interest in regional solutions. This publication addresses the technical, economic and institutional aspects of regional spent fuel storage facilities (RSFSF) and is based on the results of a series of meetings on this topic with participants from IAEA Member States. Topics discussed include safety criteria and standards, safeguards and physical protection, fuel acceptance criteria, long term stability of systems and stored fuel, selection of site, infrastructure aspects, storage technology, licensing, operations, transport, decommissioning, as well as research and development. Furthermore the publication comprises economic, financial and institutional considerations including organizations and legal aspects followed by political and public acceptance and ethical considerations. Approaches and processes for implementation are discussed, as well as the overall benefits and risks of implementing a regional facility. It is illustrated that implementing a RSFSF facility would involve simultaneously addressing a wide range of diverse challenges. The appendix to this report tabulates the numerous issues that have been touched upon in the study. It appears, however, from the discussions that the challenges can in principle be met; the RSFSF concept is technically feasible and potentially economically viable. The technical committees producing this report did not identify any obvious institutional deficiencies that would prevent completion of such a project. Storing spent fuel in a few safe, reliable, secure facilities could enhance safeguards, physical protection and non-proliferation benefits. The committee also

Technical Safety Requirements for the Waste Storage Facilities

International Nuclear Information System (INIS)

Laycak, D.T.

2010-01-01

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2009). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting

Technical Safety Requirements for the Waste Storage Facilities

Energy Technology Data Exchange (ETDEWEB)

Laycak, D T

2008-06-16

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas

Commercial LFCM vitrification technology. Quarterly progress report, October-December 1984

Energy Technology Data Exchange (ETDEWEB)

Burkholder, H.C.; Jarrett, J.H. (comps.)

1985-07-01

This report is the first in a series of quarterly reports compiled by the Nuclear Waste Treatment Program Office at Pacific Northwest Laboratory to document progress on commercial liquid-fed ceramic melter (LFCM) vitrification technology. Progress in the following technical subject areas during the first quarter of FY 1985 is discussed: pretreatment systems, melting process chemistry, glass development and characterization, feed preparation and transfer systems, melter systems, canister filling and handling systems, off-gas systems, process/product modeling and control, and supporting studies. 33 figs., 12 tabs.

Qualification and actuation of the independent technical supervision organisms in nuclear power plants and others facilities

International Nuclear Information System (INIS)

1999-09-01

This norm presents the following objectives: establishment of the Brazilian National Nuclear Energy Commission requirements for qualifying an institution as independent technical supervision organization, in a specific area of activity related to nuclear power plants and others nuclear or radioactive facilities as appropriated; regulation of the independent technical supervision and others complementary activities to be executed by an independent technical supervision organism

Technical Safety Requirements for the Waste Storage Facilities

International Nuclear Information System (INIS)

Larson, H L

2007-01-01

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

Technical Safety Requirements for the Waste Storage Facilities

Energy Technology Data Exchange (ETDEWEB)

Larson, H L

2007-09-07

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

Web server for the administrative and technical documentation of the radiodiagnostic facilities

Energy Technology Data Exchange (ETDEWEB)

Soto, M; Campayo, J. M; Guardia, V. [Logistica y Acondicionamientos Industriales SAU, Sorolla Center, Local 10, Av. de las Cortes Valencianas No. 58, 46015 Valencia (Spain); Mayo, P., E-mail: m.soto@lainsa.co [TITANIA Servicios Tecnologicos SL, Sorolla Center, Local 10, Av. de las Cortes Valencianas No. 58, 46015 Valencia (Spain)

2010-10-15

Nowadays Radiological Protection Technical Unit of LAINSA as part of Grupo Dominguis, has assigned radiological security tasks in a high number of medical X-ray facilities. It is recognised by the Nuclear Security Council as a specialist in the assessment of protection against the radiological risks associated with medical, industrial and nuclear activities. It is also authorised as an external personal dosimetry centre. Concretely medical X-ray facilities generate big amount of information because of national regulatory authority to assure the good functioning of it. This information is formed by administrative procedures for the regulatory authority in industrial and public health area, periodic quality controls of the radiographic equipment s, radiological verification in different locations to measure the radioactivity levels, certificates of employees training to work with radioactivity, dosimetric registrations of professional exposure employees and medical aptitude documents for their job, etc. In this paper it is presented a net server application to manage this information in an effective way by web. In this server each facility has an online net space with private key access and where there are all the administrative documents and nuclear security reports of the facility. Moreover, the client who is responsible of the radiological security of the centre, can have at any moment all this information, minimizing delay times and optimizing the information store support in electronic format. The objective is that this information can be updated for consulting, modifying or checking at anytime quickly and safety. All this information has to be accessible for the interested medical facility, for the Radiological Protection Technical Unit which has been contracted by the facility to do the assessment in radiological protection and for the regulatory authority in nuclear security to guarantee well-practice in medical and nuclear activities. (Author)

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.

Damage analysis and fundamental studies. Quarterly progress report, October--December 1978

Energy Technology Data Exchange (ETDEWEB)

Zwilsky, Klaus M.

1979-05-01

This report is the fourth in a series of Quarterly Technical Progress Reports on Damage Analysis and Fundamental Studies (DAFS) which is one element of the Fusion Reactor Materials Program, conducted in support of the Magnetic Fusion Energy Program. This report is organized along topical lines in parallel to a Program Plan of the same title (to be published) so that activities and accomplishments may be followed readily relative to the Program Plan. Thus, the work of a given laboratory may appear throughout the report. Chapters 1 and 2 report topics which are generic to all of the DAFS Program: DAFS Task Group Activities and Irradiation Test Facilities, respectively. Chapters 3, 4, and 5 report the work that is specific to each of the subtasks around which the program is structured: A) Environmental Characterization, B) Damage Production, and C) Damage Microstructure Evolution and Mechanical Behavior.

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.

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

Realizing Sustainability in Facilities Management: a pilot study at the Technical University of Denmark

DEFF Research Database (Denmark)

Nielsen, Susanne Balslev; Møller, Jacob Steen; Jäschke, Stefan

2012-01-01

, qualitative research and the preliminary analysis of a single, pilot case study of The Technical University of Denmark. Progress with the other complementary cases will be included in the presentation. The cases should be supplemented by more research on sustainable facilities management. Originality......, stakeholder interviews, focus groups, usability evaluations and practice-research workshops. The Technical University of Denmark (DTU) is the pilot case of an international collaboration, and more studies are planned to follow. Findings: The paper presents a framework for qualitative research on Sustainable...... Facilities Management (SFM), which can guide future research on Sustainability in FM and increase comparability between case studies. The research identifies the challenges and opportunities for integrating ecological, social and economical sustainability in university FM. The paper presents the analysis...

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

Energy Technology Data Exchange (ETDEWEB)

Chase, J.

2000-10-24

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

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

International Nuclear Information System (INIS)

Chase, J.

2000-01-01

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

Technical considerations in the design of near surface disposal facilities for radioactive waste

International Nuclear Information System (INIS)

2001-11-01

Good design is an important step towards ensuring operational as well as long term safety of low and intermediate level waste (LILW) disposal. The IAEA has produced this report with the objective of outlining the most important technical considerations in the design of near surface disposal facilities and to provide some examples of the design process in different countries. This guidance has been developed in light of experience gained from the design of existing near surface disposal facilities in a range of Member States. In particular the report provide information on design objective, design requirements, and design phases. The report focuses on: near surface disposal facilities accepting solidified LILW; disposal facilities on or just below the ground surface, where the final protective covering is of the order of a few metres thick; and disposal facilities several tens of metres below the ground surface (including rock cavern type facilities)

48 CFR 801.602-80 - Legal and technical review-Office of Construction and Facilities Management and National Cemetery...

Science.gov (United States)

2010-10-01

...-Office of Construction and Facilities Management and National Cemetery Administration. 801.602-80 Section... Responsibilities 801.602-80 Legal and technical review-Office of Construction and Facilities Management and National Cemetery Administration. An Office of Construction and Facilities Management or National Cemetery...

Basalt waste isolation project. Quarterly report, April 1, 1981-June 30, 1981

Energy Technology Data Exchange (ETDEWEB)

Deju, R.A.

1981-08-01

This document reports progress made in the Basalt Waste Isolation Project during the third quarter of fiscal year 1981. Efforts are described for the following programs of the project work breakdown structure: systems; waste package; site; repository; regulatory and institutional; test facilities; in situ test facilities.

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.

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

Geothermal direct-heat utilization assistance. Quarterly report, October--December 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

This report summarizes geothermal technical assistance, R&D and technology transfer activities of the Geo-Heat Center at Oregon Institute of Technology for the first quarter of FY-97. It describes 174 contracts with parties during this period related to technical assistance with geothermal direct heat projects. Areas dealt with include geothermal heat pumps, space heating, greenhouses, aquaculture, equipment, economics and resources. Research activities are summarized on greenhouse peaking. Outreach activities include the publication of a geothermal direct use Bulletin, dissemination of information, geothermal library, technical papers and seminars, and progress monitor reports on geothermal resources and utilization.

Damage analysis and fundamental studies. Quarterly progress report, July--September 1978

Energy Technology Data Exchange (ETDEWEB)

Zwilsky, Klaus M.

1979-05-01

This report is the third in a series of Quarterly Technical Progress Reports on Damage Analysis and Fundamental Studies (DAFS) which is one element of the Fusion Reactor Materials Program, conducted in support of the Magnetic Fusion Energy Program. This report is organized along topical lines in parallel to Section II, Damage Analysis and Fundamental Studies (DOE/ET-0032/2), of the Fusion Reactor Materials Program Plan so that activities and accomplishments may be followed readily relative to that Program Plan. Thus, the work of a given laboratory may appear throughout the report. Chapters 1 and 2 report topics which are generic to all of the DAFS Program: DAFS Task Group Activities and Irradiation Test Facilities, respectively. Chapters 3, 4, and 5 report the work that is specific to each of the subtasks around which the program is structured: A) Environmental Characterization, B) Damage Production, and C) Damage Microstructure Evolution and Mechanical Behavior.

Technical and economic assessment for asbestos abatement within Facility 20470, Wright-Patterson Air Force Base, Ohio

International Nuclear Information System (INIS)

Gibson, S.M.; Ogle, R.B.

1988-03-01

This report presents the results of a technical and economic assessment of available alternatives for asbestos abatement within Facility 20470 at the Wright-Patterson Air Force Base in Dayton, Ohio. Each alternative was screened on the basis of technical feasibility, environmental impact, economics, and fulfillment of the IRP goals. Four alternatives for study are: establishing a special operations and maintenance program; enclosure; encapsulation with sealants; and removal, disposal, and replacement. Each of these alternatives was assessed for capability to control the release of asbestos fibers within Facility 20470. Alternatives 1 and 4 were determined to be acceptable, while Alternatives 2 and 3 were found to be unacceptable. 2 refs., 6 figs

Technical Facilities Management, Loan Pool, and Calibration

Science.gov (United States)

Smith, Jacob

2011-01-01

My work at JPL for the SURF program began on June 11, 2012 with the Technical Facilities Management group (TFM). As well as TFM, I worked with Loan Pool and Metrology to help them out with various tasks. Unlike a lot of other interns, I did not have a specific project rather many different tasks to be completed over the course of the 10 weeks.The first task to be completed was to sort through old certification reports in 6 different boxes to locate reports that needed to be archived into a digital database. There were no reports within these boxes that needed to be archived but rather were to be shredded. The reports went back to the early 1980's and up to the early 2000's. I was looking for reports dated from 2002 to 2012

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

International Nuclear Information System (INIS)

Chase, J.

1998-01-01

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

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

International Nuclear Information System (INIS)

Chang Oh

2005-01-01

codes. The three categories of experiments were performed in the facility; (1) upper pool cooling trip test, (2) LOFC experiment, (3) emissivity measurement experiment. (C) Prof. NO continued Task 3. (Prof NO) The experimental work of air ingress is going on without any concern: Geometry and size effect test has been completed. The conversion factor for internal surface area was obtained through this experiment. Burn-off test was performed and the uniformity of internal reaction was confirmed. (D) INEEL engineers continued to extend the diffusion model for multiple chemical species and made some calculations. (E) Prof. Lee and Martin at University of Michigan continued to analyze the effect of the stochastic fuel on the neutronic analysis and have initiated fuel depletion calculations for the VHTGR core. Progress during the past quarter includes: Further analysis of stochastic fuel geometry; Preliminary Monte Carlo depletion of full-core VHTGR; and Installation of MCNP5 on Unix cluster

Accelerator and Technical Sector Seminar: Future neutrino facilities: the neutrino factory

CERN Multimedia

2012-01-01

Thursday 19.January 2012 at 14:15  -  IT Auditorium (bldg. 31 3-004) Future neutrino facilities: the neutrino factory by Gersende Prior / University of Geneva and CERN EN/MEF The neutrino factory is one of the proposed designs for a future intense neutrino beam facility. In its current layout, a high-power proton beam impinges on an Hg jet target producing pions, decaying in turn into muons. In order to reduce the particle beam emittance, the muon transverse momentum is reduced through ionization cooling by a technically demanding set-up made of closely-packed RF cavities alternating with absorbers. In this talk I will present the motivation for building an intense neutrino beam and some of the proposed neutrino facilities' design. I will discuss the challenges inherent to the cooling of muons, possible optimization of the current baseline and the on-going R&D. ________________ ATS Seminars Organisers: H. Burkhardt (BE), S. Sgobba (EN), G. deRijk (TE)

Third quarter 2005 sales figures

International Nuclear Information System (INIS)

2005-01-01

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

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.

High Flux Isotope Reactor quarterly report, July--September 1975

International Nuclear Information System (INIS)

McCord, R.V.; Corbett, B.L.

1975-01-01

The replacement of the permanent beryllium reflector was completed this quarter. The reactor was shut down for 87 days for this maintenance operation. Erosion of the sealing surface at the stainless steel adaptor flange on the HB-1 beam tube facility was confirmed. A soft metallic O-ring was used to effect a seal when this facility was reassembled. A comprehensive inspection of the normally inaccessible parts of the reactor pressure vessel was made. No abnormalities were found

Fast Reactor Programme. Third Quarter 1969. Progress Report

International Nuclear Information System (INIS)

Hoekstra, E.K.

1970-02-01

The RCN research programme on fast spectrum nuclear reactors comprises reactor physics, fuel performance, radiation damage in canning materials, corrosion behaviour in canning materials, aerosol research and heat transfer and hydraulics. An overview is given of the fast reactor experiments at the STEK critical facility in Petten, the Netherlands, in the third quarter of 1969

Integrated Disposal Facility FY 2012 Glass Testing Summary Report

Energy Technology Data Exchange (ETDEWEB)

Pierce, Eric M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Kerisit, Sebastien N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Krogstad, Eirik J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Burton, Sarah D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bjornstad, Bruce N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Freedman, Vicky L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Cantrell, Kirk J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Snyder, Michelle MV [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Crum, Jarrod V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westsik, Joseph H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2013-03-29

PNNL is conducting work to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility for Hanford immobilized low-activity waste (ILAW). Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program, PNNL is implementing a strategy, consisting of experimentation and modeling, to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. Key activities in FY12 include upgrading the STOMP/eSTOMP codes to do near-field modeling, geochemical modeling of PCT tests to determine the reaction network to be used in the STOMP codes, conducting PUF tests on selected glasses to simulate and accelerate glass weathering, developing a Monte Carlo simulation tool to predict the characteristics of the weathered glass reaction layer as a function of glass composition, and characterizing glasses and soil samples exhumed from an 8-year lysimeter test. The purpose of this report is to summarize the progress made in fiscal year (FY) 2012 and the first quarter of FY 2013 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of LAW glasses.

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-04-01

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

Centrifuge facilities at Technical University of Denmark

DEFF Research Database (Denmark)

Leth, Caspar Thrane; Krogsbøll, Anette Susanne; Hededal, Ole

2008-01-01

The geotechnical group at the Danish Technical University (DTU) operates a geotechnical beam centrifuge. The centrifuge was build in 1976 and has been upgraded through the years, latest with onboard data and control systems. The centrifuge concept involves an increased gravity field in which...... the physical model is placed and tested. The capabilities of the centrifuge at DTU makes it possible to obtain a scale factor of 75-85 in the tests which equals a soil volume in prototype scale of ø40m and a depth of 36 m. The centrifuge facilities at DTU have through the years been used for testing various...... geotechnical issues, such as suction anchors, tension piles in clay, active earth pressures on sheet piles and group effects for lateral loaded piles. The paper describes physical modelling in general, the centrifuge, present setups and shows samples of obtained results....

Technical concept for a greater-confinement-disposal test facility

International Nuclear Information System (INIS)

Hunter, P.H.

1982-01-01

Greater confinement disposal (GCO) has been defined by the National Low-Level Waste Program as the disposal of low-level waste in such a manner as to provide greater containment of radiation, reduce potential for migration or dispersion or radionuclides, and provide greater protection from inadvertent human and biological intrusions in order to protect the public health and safety. This paper discusses: the need for GCD; definition of GCD; advantages and disadvantages of GCD; relative dose impacts of GCD versus shallow land disposal; types of waste compatible with GCD; objectives of GCD borehole demonstration test; engineering and technical issues; and factors affecting performance of the greater confinement disposal facility

Interim Control Strategy for the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond - Two-year Update

International Nuclear Information System (INIS)

L. V. Street

2007-01-01

The Idaho Cleanup Project has prepared this interim control strategy for the U.S. Department of Energy Idaho Operations Office pursuant to DOE Order 5400.5, Chapter 11.3e (1) to support continued discharges to the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond. In compliance with DOE Order 5400.5, a 2-year review of the Interim Control Strategy document has been completed. This submittal documents the required review of the April 2005 Interim Control Strategy. The Idaho Cleanup Project's recommendation is unchanged from the original recommendation. The Interim Control Strategy evaluates three alternatives: (1) re-route the discharge outlet to an uncontaminated area of the TSF-07; (2) construct a new discharge pond; or (3) no action based on justification for continued use. Evaluation of Alternatives 1 and 2 are based on the estimated cost and implementation timeframe weighed against either alternative's minimal increase in protection of workers, the public, and the environment. Evaluation of Alternative 3, continued use of the TSF-07 Disposal Pond under current effluent controls, is based on an analysis of four points: - Record of Decision controls will protect workers and the public - Risk of increased contamination is low - Discharge water will be eliminated in the foreseeable future - Risk of contamination spread is acceptable. The Idaho Cleanup Project recommends Alternative 3, no action other than continued implementation of existing controls and continued deactivation, decontamination, and dismantlement efforts at the Test Area North/Technical Support Facility

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.

IsoDAR@KamLAND: A Conceptual Design Report for the Technical Facility

CERN Document Server

Abs, M; Alonso, J R; Axani, S; Barletta, W A; Barlow, R; Bartoszek, L; Bungau, A; Calabretta, L; Calanna, A; Campo, D; Castro, G; Celona, L; Collin, G H; Conrad, J M; Gammino, S; Johnson, R; Karagiorgi, G; Kayser, S; Kleeven, W; Kolano, A; Labrecque, F; Loinaz, W A; Minervini, J; Moulai, M H; Okuno, H; Owen, H; Papavassiliou, V; Shaevitz, M H; Shimizu, I; Shokair, T M; Sorensen, K F; Spitz, J; Toups, M; Vagins, M; Van Bibber, K; Wascko, M O; Winklehner, D; Winslow, L A; Yang, J J

2015-01-01

This conceptual design report describes the technical facility for the IsoDAR electron-antineutrino source at KamLAND. The IsoDAR source will allow an impressive program of neutrino oscillation and electroweak physics to be performed at KamLAND. This report provides information on the physics case, the conceptual design for the subsystems, alternative designs considered, specifics of installation at KamLAND, and identified needs for future development. We discuss the risks we have identified and our approach to mitigating those risks with this design. A substantial portion of the conceptual design is based on three years of experimental efforts and on industry experience. This report also includes information on the conventional facilities.

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.

Engineering study: Fast Flux Test Facility fuel reprocessing

International Nuclear Information System (INIS)

Beary, M.M.; Raab, G.J.; Reynolds, W.R. Jr.; Yoder, R.A.

1974-01-01

Several alternatives were studied for reprocessing FFTF fuels at Hanford. Alternative I would be to decontaminate and trim the fuel at T Plant and electrolytically dissolve the fuel at Purex. Alternative II would be to decontaminate and shear leach the fuels in a new facility near Purex. Alternative III would be to decontaminate and store fuel elements indefinitely at T Plant for subsequent offsite shipment. Alternative I, 8 to 10 M$ and 13 quarter-years; for Alternative II, 24 to 28 M$ and 20 quarter-years; for Alternative III, 3 to 4 M$ and 8 quarter-years. Unless there is considerable slippage in the FFTF shipping schedule, it would not be possible to build a new facility as described in Alternative II in time without building temporary storage facilities at T Plant, as described in Alternative III

The magnetohydrodynamics Coal-Fired Flow Facility

Energy Technology Data Exchange (ETDEWEB)

1991-07-01

In this quarterly technical progress report, UTSI summarizes the results of a multi-task research and development project directed toward the development of the technology for the commercialization of the steam bottoming plant for the MHD steam combined cycle power plant. The report covers the final test in a 2000-hour proof-of-concept (POC) test series on eastern coal, the plans and progress for the facility modifications and the conduct of the POC tests to be conducted with western coal. Results summarized in the report include chloride emissions from the particle removal (ESP/BH) processes, nitrogen and sulfur oxide emissions for various tests conditions, measurements of particulate control efficiency and management of the facility holding ponds during testing. Activities relating to corrosion and deposition probe measurements during testing and the fouling of heat transfer tubes and interaction with sootblowing cycles are summarized. The performance of both UTSI and Mississippi State University (MSU) advanced diagnostic systems is reported. Significant administrative and contractual actions are included. 2 refs., 28 figs., 7 tabs.

Geothermal direct-heat utilization assistance. Quarterly project progress report, October--December 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-01-01

This report summarizes geothermal technical assistance, R and D and technology transfer activities of the Geo-Heat Center at Oregon Institute of Technology for the first quarter of FY-98 (October--December 1997). It describes 216 contacts with parties during this period related to technical assistance with geothermal direct heat projects. Areas dealt with include requests for general information including maps and material for high school debates, and material on geothermal heat pumps, resource and well data, space heating and cooling, greenhouses, aquaculture, equipment, district heating, resorts and spas, industrial applications, electric power and snow melting. Research activities include work on model construction specifications of lineshaft submersible pumps and plate heat exchangers, a comprehensive aquaculture developer package and revisions to the Geothermal Direct Use Engineering and Design Guidebook. Outreach activities include the publication of the Quarterly Bulletin (Vol. 18, No. 4) which was devoted entirely to geothermal activities in South Dakota, dissemination of information mainly through mailings of publications, tours of local geothermal uses, geothermal library acquisition and use, participation in workshops, short courses and technical meetings by the staff, and progress monitor reports on geothermal activities.

Interim Control Strategy for the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond - Two-year Update

Energy Technology Data Exchange (ETDEWEB)

L. V. Street

2007-04-01

The Idaho Cleanup Project has prepared this interim control strategy for the U.S. Department of Energy Idaho Operations Office pursuant to DOE Order 5400.5, Chapter 11.3e (1) to support continued discharges to the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond. In compliance with DOE Order 5400.5, a 2-year review of the Interim Control Strategy document has been completed. This submittal documents the required review of the April 2005 Interim Control Strategy. The Idaho Cleanup Project's recommendation is unchanged from the original recommendation. The Interim Control Strategy evaluates three alternatives: (1) re-route the discharge outlet to an uncontaminated area of the TSF-07; (2) construct a new discharge pond; or (3) no action based on justification for continued use. Evaluation of Alternatives 1 and 2 are based on the estimated cost and implementation timeframe weighed against either alternative's minimal increase in protection of workers, the public, and the environment. Evaluation of Alternative 3, continued use of the TSF-07 Disposal Pond under current effluent controls, is based on an analysis of four points: - Record of Decision controls will protect workers and the public - Risk of increased contamination is low - Discharge water will be eliminated in the foreseeable future - Risk of contamination spread is acceptable. The Idaho Cleanup Project recommends Alternative 3, no action other than continued implementation of existing controls and continued deactivation, decontamination, and dismantlement efforts at the Test Area North/Technical Support Facility.

(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.

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

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).

Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Presentations

International Nuclear Information System (INIS)

2013-01-01

The objectives of the meeting were: • To identify the main issues and technical features that affect capital and energy production costs of fast reactors and related fuel cycle facilities; • To present fast reactor concepts and designs with enhanced economic characteristics, as well as innovative technical solutions (components, subsystems, etc.) that have the potential to reduce the capital costs of fast reactors and related fuel cycle facilities; • To present energy models and advanced tools for the cost assessment of innovative fast reactors and associated nuclear fuel cycles; • To discuss the results of studies and ongoing R&D activities that address cost reduction and the future economic competitiveness of fast reactors; • To identify research and technology development needs in the field, also in view of new IAEA initiatives to help and support Member States in improving the economic competitiveness of fast reactors and associated nuclear fuel cycles

Safety of and regulations for nuclear fuel cycle facilities. Report of a technical committee meeting

International Nuclear Information System (INIS)

2001-05-01

In order to compile information on the nature of the safety concerns and current status of the regulations concerning nuclear fuel cycle facilities in Member States, an IAEA Technical Committee meeting on this topic was convened from 8 to 12 May 2000 in Vienna. The present publication contains the results of this meeting. The contributions of the participants in Annex 3 exemplify the work done in some Member States to develop an adequate regulatory framework to oversee the safe operation of these facilities

(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.

Experimental Facilities Division/User Program Division technical progress report 1999-2000

International Nuclear Information System (INIS)

2001-01-01

In October 1999, the two divisions of the Advanced Photon Source (APS), the Accelerator Systems Division (ASD) and the Experimental Facilities Division (XFD), were reorganized into four divisions (see high-level APS organizational chart, Fig. 1.1). In addition to ASD and XFD, two new divisions were created, the APS Operations Division (AOD), to oversee APS operations, and the User Program Division (UPD), to serve the APS user community by developing and maintaining the highest quality user technical and administration support. Previous XFD Progress Reports (ANL/APS/TB-30 and ANL/APS/TB-34) covered a much broader base, including APS user administrative support and what was previously XFD operations (front ends, interlocks, etc.) This Progress Report summarizes the main scientific and technical activities of XFD, and the technical support, research and development (R and D) activities of UPD from October 1998 through November 2000. The report is divided into four major sections, (1) Introduction, (2) SRI-CAT Beamlines, Technical Developments, and Scientific Applications, (3) User Technical Support, and (4) Major Plans for the Future. Sections 2 and 3 describe the technical activities and research accomplishments of the XFD and UPD personnel in supporting the synchrotron radiation instrumentation (SRI) collaborative access team (CAT) and the general APS user community. Also included in this report is a comprehensive list of publications (Appendix 1) and presentations (Appendix 2) by XFD and UPD staff during the time period covered by this report. The organization of section 2, SRI CAT Beamlines, Technical Developments, and Scientific Applications has been made along scientific techniques/disciplines and not ''geographical'' boundaries of the sectors in which the work was performed. Therefore items under the subsection X-ray Imaging and Microfocusing could have been (and were) performed on several different beamlines by staff in different divisions. The management of

Functional design criteria for an exploratory shaft facility in salt: Technical report

International Nuclear Information System (INIS)

1986-11-01

The purpose of the Functional Criteria for Design is to provide technical direction for the development of detailed design criteria for the exploratory shaft facility. This will assure that the exploratory shaft facility will be designed in accordance with the current Mission Plan as well as the Nuclear Waste Policy Act and 10 CFR Part 60, which will facilitate the licensing process. The functional criteria for design are not intended to limit or constrain the designer's flexibility. The following philosophies will be incorporated in the designs: (1) The exploratory shaft will be designed to fulfill its intended purpose which is to characterize the salt site by subsurface testing; (2) the design will minimize any adverse impact which the facility may cause to the environment and any damage to the site if it should be found suitable for a repository; (3) the health and safety of the public and of the workers will be an essential factor in the design; (4) sound engineering principles and practices will be consistently employed in the design process; (5) the exploratory shaft and related surface and subsurface facilities will be designed to be economical and reliable in construction, operation, and maintenance; and (6) the exploratory shaft facility will be designed in accordance with applicable federal, state, and local regulations, as well as all applicable national consensus codes and standards

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.

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.

Quarterly report of the Nuclear Power Inspectorate October - December 1981

International Nuclear Information System (INIS)

1982-01-01

The Inspectorate is the supervising authority of nuclear installations. The disturbances of reactor operations during the 4th quarter are described, e.g. 9 reactor trips. The operation of waste processing at Forsmark is discussed and the inspection of the facilities of ASEA-ATOM and Studsvik Energiteknik are dealt with. (G.B.)

Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility

International Nuclear Information System (INIS)

Gates, R.; Glukhov, A.; Markowski, F.

1996-06-01

This technical report is a comprehensive evaluation of the proposal by the Ukrainian State Committee on Nuclear Power Utilization to create a central facility for radioactive waste (not spent fuel) processing. The central facility is intended to process liquid and solid radioactive wastes generated from all of the Ukrainian nuclear power plants and the waste generated as a result of Chernobyl 1, 2 and 3 decommissioning efforts. In addition, this report provides general information on the quantity and total activity of radioactive waste in the 30-km Zone and the Sarcophagus from the Chernobyl accident. Processing options are described that may ultimately be used in the long-term disposal of selected 30-km Zone and Sarcophagus wastes. A detailed report on the issues concerning the construction of a Ukrainian Central Radioactive Waste Processing Facility (CRWPF) from the Ukrainian Scientific Research and Design institute for Industrial Technology was obtained and incorporated into this report. This report outlines various processing options, their associated costs and construction schedules, which can be applied to solving the operating and decommissioning radioactive waste management problems in Ukraine. The costs and schedules are best estimates based upon the most current US industry practice and vendor information. This report focuses primarily on the handling and processing of what is defined in the US as low-level radioactive wastes

Technical Support Section Instrument Support Program for nuclear and nonnuclear facilities with safety requirements

International Nuclear Information System (INIS)

Adkisson, B.P.; Allison, K.L.

1995-01-01

This document describes requirements, procedures, and supervisory responsibilities of the Oak Ridge National Laboratory (ORNL) Instrumentation and Controls (I ampersand C) Division's Technical Support Section (TSS) for instrument surveillance and maintenance in nonreactor nuclear facilities having identified Operational Safety Requirements (OSRs) or Limiting Conditions Document (LCDs). Implementation of requirements comply with the requirements of U.S. Department of Energy (DOE) Orders 5480.5, 5480.22, and 5481.1B; Martin Marietta Energy Systems, Inc. (Energy Systems), Policy Procedure ESS-FS-201; and ORNL SPP X-ESH-15. OSRs and LCDs constitute an agreement or contract between DOE and the facility operating management regarding the safe operation of the facility. One basic difference between OSRs and LCDs is that violation of an OSR is considered a Category II occurrence, whereas violation of an LCD requirement is considered a Category III occurrence (see Energy Systems Standard ESS-OP-301 and ORNL SPP X-GP-13). OSRs are required for high- and moderate-hazard nuclear facilities, whereas the less-rigorous LCDs are required for low-hazard nuclear facilities and selected open-quotes generally acceptedclose quotes operations. Hazard classifications are determined through a hazard screening process, which each division conducts for its facilities

Quarterly environmental radiological survey summary - first quarter 1997 100, 200, 300, and 600 areas

International Nuclear Information System (INIS)

Mckinney, S.M.

1997-01-01

This report provides a summary of the radiological surveys performed in support of near-facility environmental monitoring at the Hanford Site. The First Quarter 1997 survey results and the status of actions required are summarized below: (1) All of the routine environmental radiological surveys scheduled during January, February, and March 1997, were performed as planned. (2) One hundred four environmental radiological surveys were performed during the first quarter 1997, twenty-nine at the active waste sites and seventy-five at the inactive waste sites. Contamination above background levels was found at eight of the active waste sites and seven of the inactive waste sites. Contamination levels as high as >1,000,000 disintegrations per minute (dpm) were reported. Of these contaminated surveys twelve were in Underground Radioactive Material (URM) areas and three were in contamination areas. The contamination found within ten of the URM areas was immediately cleaned up and no further action was required. In the remaining five sites the areas were posted and will require decontamination. Radiological Problem Reports (RPR's) were issued and the sites were turned over to the landlord for further action if required. (3) During the first quarter of 1997, 5.6 hectares (13.8 acres) were stabilized and radiologically down posted from Contamination Area (CA)/Soil Contamination (SC) to URM. (4) During the first quarter of 1997, the size of 216-A-25 Gable Mountain Pond was increased from 30.4 to 34.5 hectares (75.0 to 85.2 acres). This increase in size was due to the correction of the original boundary area by using the advanced technology of a global positioning system (GPS). An area, 1.6 hectares (4.0 acres), east of and adjacent to the 241-S/SX/SY tank farm complex was posted as a contamination/soil contamination area. (5) Five open Surveillance Compliance Inspection Reports (SCIRs) had not been resolved

The TOPFLOW multi-purpose thermohydraulic test facility

International Nuclear Information System (INIS)

Schaffrath, Andreas; Kruessenberg, A.-K.; Weiss, F.-P.; Prasser, H.-M.

2002-01-01

The TOPFLOW (Transient Two Phase Flow Test Facility) multi-purpose thermohydraulic test facility is being built for studies of steady-state and transient flow phenomena in two-phase flows, and for the development and validation of the models contained in CFD (Computational Fluid Dynamics) codes. The facility is under construction at the Institute for Safety Research of the Rossendorf Research Center (FZR). It will be operated together with the Dresden Technical University and the Zittau/Goerlitz School for Technology, Economics and Social Studies within the framework of the Nuclear Technology Competence Preservation Program. TOPFLOW, with its test sections and its flexible concept, is available as an attractive facility also to users from all European countries. Experiments are planned in these fields, among others: - Transient two-phase flows in vertical and horizontal pipes and pipes of any inclination as well as in geometries typical of nuclear reactors (annulus, hot leg). - Boiling in large vessels and water pools (measurements of steam generation, 3D steam content distribution, turbulence, temperature stratification). - Test of passive components and safety systems. - Condensation in horizontal pipes in the absence and presence of non-condensable gases. The construction phase of TOPFLOW has been completed more or less on schedule. Experiments can be started after a commissioning phase in the 3rd quarter of 2002. (orig.) [de

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).

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).

[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.

Accelerator technical design report for high-intensity proton accelerator facility project, J-PARC

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-03-01

This report presents the detail of the technical design of the accelerators for the High-Intensity Proton Accelerator Facility Project, J-PARC. The accelerator complex comprises a 400-MeV room-temperature linac (600-MeV superconducting linac), 3-GeV rapid-cycling synchrotron (RCS), and a 50-GeV synchrotron (MR). The 400-MeV beam is injected to the RCS, being accelerated to 3 GEV. The 1-MW beam thus produced is guided to the Materials Life Science Experimental Facility, with both the pulsed spallation neutron source and muon source. A part of the beam is transported to the MR, which provides the 0.75-MW beam to either the Nuclear and Fundamental Particle Experimental Facility or the Neutrino Production Target. On the other hand, the beam accelerated to 600 MeV by the superconducting linac is used for the Nuclear Waster Transmutation Experiment. In this way, this facility is unique, being multipurpose one, including many new inventions and Research and Development Results. This report is based upon the accomplishments made by the Accelerator Group and others of the Project Team, which is organized on the basis of the Agreement between JAERI and KEK on the Construction and Research and Development of the High-Intensity Proton Accelerator Facility. (author)

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

Regulatory and technical reports (abstract index journal): Annual compilation for 1994. Volume 19, Number 4

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-03-01

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. 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.

Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Working Material

International Nuclear Information System (INIS)

2013-01-01

The objectives of the meeting were: - To identify the main issues and technical features that affect capital and energy production costs of fast reactors and related fuel cycle facilities; - To present fast reactor concepts and designs with enhanced economic characteristics, as well as innovative technical solutions (components, subsystems, etc.) that have the potential to reduce the capital costs of fast reactors and related fuel cycle facilities; - To present energy models and advanced tools for the cost assessment of innovative fast reactors and associated nuclear fuel cycles; - To discuss the results of studies and on-going R&D activities that address cost reduction and the future economic competitiveness of fast reactors; and - To identify research and technology development needs in the field, also in view of new IAEA initiatives to help and support Member States in improving the economic competitiveness of fast reactors and associated nuclear fuel cycles

Liquid Effluent Retention Facility/Effluent Treatment Facility Hazards Assessment

International Nuclear Information System (INIS)

Simiele, G.A.

1994-01-01

This document establishes the technical basis in support of Emergency Planning activities for the Liquid Effluent Retention Facility and Effluent Treatment Facility the Hanford Site. The document represents an acceptable interpretation of the implementing guidance document for DOE ORDER 5500.3A. Through this document, the technical basis for the development of facility specific Emergency Action Levels and the Emergency Planning Zone is demonstrated

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

International Nuclear Information System (INIS)

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

1995-07-01

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

EMSL Quarterly Highlights Report Second Quarter, Fiscal Year 2010 (January 1, 2010 through March 31, 2010)

Energy Technology Data Exchange (ETDEWEB)

West, Staci A.; Showalter, Mary Ann; Manke, Kristin L.; Carper, Ross R.; Wiley, Julie G.; Beckman, Mary T.

2010-04-20

The Environmental Molecular Sciences Laboratory (EMSL) is a U.S. Department of Energy (DOE) national scientific user facility located at Pacific Northwest National Laboratory (PNNL) in Richland, Washington. EMSL is operated by PNNL for the DOE-Office of Biological and Environmental Research. At one location, EMSL offers a comprehensive array of leading-edge resources and expertise. Access to the instrumentation and expertise is obtained on a peer-reviewed proposal basis. Staff members work with researchers to expedite access to these capabilities. The "EMSL Quarterly Highlights Report" documents current research and activities of EMSL staff and users.

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.

Comparison of Perceived and Technical Healthcare Quality in Primary Health Facilities: Implications for a Sustainable National Health Insurance Scheme in Ghana.

Science.gov (United States)

Alhassan, Robert Kaba; Duku, Stephen Opoku; Janssens, Wendy; Nketiah-Amponsah, Edward; Spieker, Nicole; van Ostenberg, Paul; Arhinful, Daniel Kojo; Pradhan, Menno; Rinke de Wit, Tobias F

2015-01-01

Quality care in health facilities is critical for a sustainable health insurance system because of its influence on clients' decisions to participate in health insurance and utilize health services. Exploration of the different dimensions of healthcare quality and their associations will help determine more effective quality improvement interventions and health insurance sustainability strategies, especially in resource constrained countries in Africa where universal access to good quality care remains a challenge. To examine the differences in perceptions of clients and health staff on quality healthcare and determine if these perceptions are associated with technical quality proxies in health facilities. Implications of the findings for a sustainable National Health Insurance Scheme (NHIS) in Ghana are also discussed. This is a cross-sectional study in two southern regions in Ghana involving 64 primary health facilities: 1,903 households and 324 health staff. Data collection lasted from March to June, 2012. A Wilcoxon-Mann-Whitney test was performed to determine differences in client and health staff perceptions of quality healthcare. Spearman's rank correlation test was used to ascertain associations between perceived and technical quality care proxies in health facilities, and ordered logistic regression employed to predict the determinants of client and staff-perceived quality healthcare. Negative association was found between technical quality and client-perceived quality care (coef. = -0.0991, pquality proxies, suggesting some level of unbalanced commitment to quality improvement and potential information asymmetry between clients and service providers. Overall, the findings suggest that increased efforts towards technical quality care alone will not necessarily translate into better client-perceived quality care and willingness to utilize health services in NHIS-accredited health facilities. There is the need to intensify client education and balanced

Comparison of Perceived and Technical Healthcare Quality in Primary Health Facilities: Implications for a Sustainable National Health Insurance Scheme in Ghana.

Directory of Open Access Journals (Sweden)

Robert Kaba Alhassan

Full Text Available Quality care in health facilities is critical for a sustainable health insurance system because of its influence on clients' decisions to participate in health insurance and utilize health services. Exploration of the different dimensions of healthcare quality and their associations will help determine more effective quality improvement interventions and health insurance sustainability strategies, especially in resource constrained countries in Africa where universal access to good quality care remains a challenge.To examine the differences in perceptions of clients and health staff on quality healthcare and determine if these perceptions are associated with technical quality proxies in health facilities. Implications of the findings for a sustainable National Health Insurance Scheme (NHIS in Ghana are also discussed.This is a cross-sectional study in two southern regions in Ghana involving 64 primary health facilities: 1,903 households and 324 health staff. Data collection lasted from March to June, 2012. A Wilcoxon-Mann-Whitney test was performed to determine differences in client and health staff perceptions of quality healthcare. Spearman's rank correlation test was used to ascertain associations between perceived and technical quality care proxies in health facilities, and ordered logistic regression employed to predict the determinants of client and staff-perceived quality healthcare.Negative association was found between technical quality and client-perceived quality care (coef. = -0.0991, p<0.0001. Significant staff-client perception differences were found in all healthcare quality proxies, suggesting some level of unbalanced commitment to quality improvement and potential information asymmetry between clients and service providers. Overall, the findings suggest that increased efforts towards technical quality care alone will not necessarily translate into better client-perceived quality care and willingness to utilize health services in

Technical review and evaluation for the installation of cold neutron source facility at HANARO

International Nuclear Information System (INIS)

Choi, Chang Woong; Kim, Dong Hoon; Lee, Mu Woong; Cho, Man Soon; Oh, Yun Woo; Park, Sun Hee; Park, Kuk Nam; Lee, Chang Hee

1996-01-01

The principle subjects of this study are to analyze the technical characteristics of cold neutron source(CNS) and take measures to cope with the matters regarding the installation of CNS facility at HANARO. This report, thus, reviews the current status of the CNS facilities that are now in operation worldwide and classifies the system and equipment to select the appropriate type for HANARO and provides advice and guidance for the future basic and detail design. As we have none of CNS facility here and very few experienced persons yet, this report provides some information for domestic users through the investigation of the utilization fields and experimental facilities of CNS, and presents the estimated total cost for the project based on JRR-3M. In addition, the work scope of the conceptual design, which will be performed in advance of the basic and detail design, and cooperative program with the countries having the advanced technology of CNS is presented in this report. 43 tabs., 57 figs., 22 refs. (Author)

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

Energy Technology Data Exchange (ETDEWEB)

Meyerhofer, D.D. [ed.

1992-12-31

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

My Career and the "Rhetoric of" Technical Writing and Communication

Science.gov (United States)

Schuster, Mary Lay

2015-01-01

This article traces the history of Mary Schuster's career in technical writing and communication from 1968 when she took a position in the Publications Department at the Institute of Electrical and Electronics Engineers (IEEE) to her work at "Technical Communication Quarterly" ("TCQ") in 2003 and forward. She discusses the…

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.

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).

Expansion of the Geo-Heat Quarterly Bulletin. Final report, 15 June 1978-30 June 1979

Energy Technology Data Exchange (ETDEWEB)

Lienau, P.J.

1979-06-30

The work of the Center is described in the areas of: public information dissemination service, technical assistance to developers, regional resource planning, and applied research projects. Included in the appendix are four issues of the Geo-Heat Utilization Center Quarterly Bulletin. (MHR)

Technical Support and Transfer of Geothrmal Technical Knowledge and Information

Energy Technology Data Exchange (ETDEWEB)

John W. Lund; Toni" Boyd

2007-11-14

The Geo-Heat Center (GHC) staff provided responses to 1442 technical support requests during the contract period (April 1, 2006 to September 30, 2007), which were six quarters under this contract. Our website, consisting of 1900 files, also contributes to our technical assistance activity. Downloaded files were 1,889,323 (3,448 per day) from our website, the total number of users was 1,365,258 (2,491 per day), and the total number of hits were 6,008,500 (10,064 per day). The GHC staff attended 60 workshops, short course and professional meeting and made 29 technical presentations. The staff also prepared and mailed out 2,000 copies of each of five issues of the GHC Quaterly Bulletin which contained 26 articles. We also mailed out approximately 5,000 papers and publications to interested individuals and organizations.

Results For The Third Quarter 2013 Tank 50 WAC Slurry Sample

Energy Technology Data Exchange (ETDEWEB)

Bannochie, Christopher J.

2013-11-26

This report details the chemical and radionuclide contaminant results for the characterization of the 2013 Third Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC) in effect at that time. Information from this characterization will be used by DWPF & Saltstone Facility Engineering (DSFE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System.

Treatment of Race/Ethnicity in Career-Technical Education Research

Science.gov (United States)

Rojewski, Jay W.; Xing, Xue

2013-01-01

This study examined how researchers of career-technical education have treated the construct of race/ethnicity in recent studies. Fifty-one of 71 articles published in the Career and Technical Education Research (CTER) over a 7-year span (2005-2011) were included. A content analysis found that only one quarter (n = 13, 25.49%) of eligible studies…

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.

Regulatory and technical reports (abstract index journal)

International Nuclear Information System (INIS)

1994-06-01

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

9 CFR 351.10 - Facilities.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Facilities. 351.10 Section 351.10... CERTIFICATION CERTIFICATION OF TECHNICAL ANIMAL FATS FOR EXPORT Facilities and Operations § 351.10 Facilities. (a) Facilities for the preparation, identification, and storage of the technical animal fat to be...

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.

Short-Term Energy Outlook: Quarterly projections. Fourth quarter 1993

Energy Technology Data Exchange (ETDEWEB)

1993-11-05

The Energy Information Administration (EIA) prepares quarterly, short-term energy supply, demand, and price projections for publication in February, May, August, and November in the Short-Term Energy Outlook (Outlook). An annual supplement analyzes the performance of previous forecasts, compares recent cases with those of other forecasting services, and discusses current topics related to the short-term energy markets. (See Short-Term Energy Outlook Annual Supplement, DOE/EIA-0202.) The forecast period for this issue of the Outlook extends from the fourth quarter of 1993 through the fourth quarter of 1994. Values for the third quarter of 1993, however, are preliminary EIA estimates (for example, some monthly values for petroleum supply and disposition are derived in part from weekly data reported in the Weekly Petroleum Status Report) or are calculated from model simulations using the latest exogenous information available (for example, electricity sales and generation are simulated using actual weather data). The historical energy data are EIA data published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications.

Establishing the SECME Model in the District of Columbia. Quarterly report, September 1, 1993--December 31, 1993

Energy Technology Data Exchange (ETDEWEB)

1993-12-31

Technical progress and Federal Cash Transaction reports are presented for the first quarter. The work has been valuable in providing opportunities for greater academic achievement in mathematics and science for minority students in the District of Columbia.

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

International Nuclear Information System (INIS)

1996-04-01

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

Dependability of technical items: Problems of standardization

Science.gov (United States)

Fedotova, G. A.; Voropai, N. I.; Kovalev, G. F.

2016-12-01

This paper is concerned with problems blown up in the development of a new version of the Interstate Standard GOST 27.002 "Industrial product dependability. Terms and definitions". This Standard covers a wide range of technical items and is used in numerous regulations, specifications, standard and technical documentation. A currently available State Standard GOST 27.002-89 was introduced in 1990. Its development involved a participation of scientists and experts from different technical areas, its draft was debated in different audiences and constantly refined, so it was a high quality document. However, after 25 years of its application it's become necessary to develop a new version of the Standard that would reflect the current understanding of industrial dependability, accounting for the changes taking place in Russia in the production, management and development of various technical systems and facilities. The development of a new version of the Standard makes it possible to generalize on a terminological level the knowledge and experience in the area of reliability of technical items, accumulated over a quarter of the century in different industries and reliability research schools, to account for domestic and foreign experience of standardization. Working on the new version of the Standard, we have faced a number of issues and problems on harmonization with the International Standard IEC 60500-192, caused first of all by different approaches to the use of terms and differences in the mentalities of experts from different countries. The paper focuses on the problems related to the chapter "Maintenance, restoration and repair", which caused difficulties for the developers to harmonize term definitions both with experts and the International Standard, which is mainly related to differences between the Russian concept and practice of maintenance and repair and foreign ones.

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)

Short-term energy outlook: Quarterly projections, fourth quarter 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-10-14

The Energy Information Administration (EIA) prepares quarterly short-term energy supply, demand, and price projections for printed publication in January, April, July, and October in the Short-Term Energy Outlook. The details of these projections, as well as monthly updates on or about the 6th of each interim month, are available on the internet at: www.eia.doe.gov/emeu/steo/pub/contents.html. The forecast period for this issue of the Outlook extends from the fourth quarter of 1997 through the fourth quarter of 1998. Values for the fourth quarter of 1997, however, are preliminary EIA estimates (for example, some monthly values for petroleum supply and disposition are derived in part from weekly data reported in EIA`s Weekly Petroleum Status Report) or are calculated from model simulations that use the latest exogenous information available (for example, electricity sales and generation are simulated by using actual weather data). The historical energy data, compiled in the fourth quarter 1997 version of the Short-Term Integrated Forecasting System (STIFS) database, are mostly EIA data regularly published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications. Minor discrepancies between the data in these publications and the historical data in this Outlook are due to independent rounding. The STIFS model is driven principally by three sets of assumptions or inputs: estimates of key macroeconomic variables, world oil price assumptions, and assumptions about the severity of weather. 19 tabs.

Consolidated Reprocessing Progam. Quarterly progress report ending February 28, 1979

International Nuclear Information System (INIS)

1979-03-01

This publication continues the quarterly series presenting results of work performed under the Consolidated Reprocessing Program at General Atomic Company. Results of work on this program prior to June 1974 were included in a quarterly series on the HTGR Base Program. The work reported includes the development of unit processes and equipment for reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel, the design and development of an integrated pilot line to demonstrate the head end of HTGR reprocessing using unirradiated fuel materials, and design work in support of Hot Engineering Tests (HET). Work is also described on trade-off studies concerning the required design of facilities and equipment for the large-scale recycle of HTGR fuels in order to guide the development activities for HTGR fuel recycle

Technical evaluation report of the Fort St. Vrain final draft upgraded technical specifications

International Nuclear Information System (INIS)

Kimura, C.Y.

1989-01-01

This report is a technical evaluation of the final draft of the Fort St. Vrain (FSV) Upgraded Technical Specifications (UT/S) as issued by Public Service of Colorado (PSC) on May 27, 1988 with subsequent supplemental updates issued on June 15, 1988 and August 5, 1988. It has been compared for consistency, and safety conservatism with the Fort St. Vrain (FSV) Updated Final Safety Analysis Report (FSAR), the FSV Safety Evaluation Report (SER), the Facility Operating License, DPR-34, and all amendments to the Facility Operating License issued as of June 1, 1988, and Appendix A to the Operating License DPR-34, Technical Specifications. Because of the age of the plant, no supplements to the Fort St. Vrain SER have been issued since the original SER was not issued as a WASH or a NUREG report. This made it necessary to review all amendments to the Facility Operating License since they would contain the safety evaluations done to support changes to the Facility Operating License. The upgraded Fort St. Vrain Technical Specifications were also broadly compared with the latest Westinghouse Standard Technical Specifications (WSTS) to assure that what was proposed for Fort St. Vrain was consistent with the latest NRC staff practices for standard technical specifications

Technical quality of delivery care in private- and public-sector health facilities in Enugu and Lagos States, Nigeria.

Science.gov (United States)

Hirose, Atsumi; Yisa, Ibrahim O; Aminu, Amina; Afolabi, Nathanael; Olasunmbo, Makinde; Oluka, George; Muhammad, Khalilu; Hussein, Julia

2018-06-01

Private-sector providers are increasingly being recognized as important contributors to the delivery of healthcare. Countries with high disease burdens and limited public-sector resources are considering using the private sector to achieve universal health coverage. However, evidence for the technical quality of private-sector care is lacking. This study assesses the technical quality of maternal healthcare during delivery in public- and private-sector facilities in resource-limited settings, from a systems and programmatic perspective. A summary index (the skilled attendance index, SAI), was used. Two-staged cluster sampling with stratification was used to select representative samples of case records in public- and private-sector facilities in Enugu and Lagos States, Nigeria. Information to assess criteria was extracted, and the SAI calculated. Linear regression models examined the relationship between SAI and the private and public sectors, controlling for confounders. The median SAI was 54.8% in Enugu and 85.7% in Lagos. The private for-profit sector's SAI was lower than and the private not-for-profit sector's SAI was higher than the public sector in Enugu [coefficient = -3.6 (P = 0.018) and 12.6 (P private for-profit sector's SAI was higher and the private not-for-profit sector's SAI was lower than the public sector [3.71 (P = 0.005) and -3.92 (P private for-profit providers' care was poorer than public providers where the public provision of care was weak, while private for-profit facilities provided better technical quality care than public facilities where the public sector was strong and there was a relatively strong regulatory body. Our findings raise important considerations relating to the quality of maternity care, the public-private mix and needs for regulation in global efforts to achieve universal healthcare.

Management of aging in technical facilities of E.ON Kernkraft plants; Alterungsmanagement bei technischen Einrichtungen in Anlagen der E.ON Kernkraft GmbH

Energy Technology Data Exchange (ETDEWEB)

Reese, Sven H.; Brast, Gerhard [E.ON Kernkraft GmbH, Hannover (Germany); Schoeckle, Friedrich [AMTEC Messtechnischer Service GmbH, Lauffen/N (Germany)

2009-11-15

The publication explains, by means of specific measures, the management of aging in technical facilities as practiced in the plants of E.ON Kernkraft GmbH. First, the historical background is outlined and the reasons for introducing management of aging in order to limit and control factors influencing the lifetime of nuclear power plants are described. This is followed by a definition of management of aging in important safety-related facilities as against lifetime management of technical systems relevant to plant availability. This is the context in which the scope of the survey of continuous management of aging is defined in respect of physical aging. A classification is then made in accordance with the staggered requirements to be met in the quality of technical facilities. On the basis of the quality to be assured, the different component groups are assigned corresponding operational measures and explained. These continuous measures extend from failure-oriented maintenance to preventive maintenance to the integrity concept for technical installations. To document the findings and evaluate the effectiveness of the measures taken, the integration of the process is described and reference is made to continuous optimization according to PDCA principles. The explicit introduction of the process of management of aging creates a platform which allows a documentation to be accumulated of the manifold and comprehensive measures taken to control phenomena of aging in technical installations. (orig.)

Technical merits and leadership in facility management

OpenAIRE

Shoemaker, Jerry J

1997-01-01

After almost ten years of experience and formal education in design, construction, and facility operations and maintenance, the challenges and complexity of facility management still seem overwhelming and intangible. This document explores those complexities and challenges, and presents several philosophies and strategies practiced in facility management. The document is divided into six chapters; the introduction, facility management and leadership, building systems, facility operations, fac...

Longitudinal variation in pressure injury incidence among long-term aged care facilities.

Science.gov (United States)

Jorgensen, Mikaela; Siette, Joyce; Georgiou, Andrew; Westbrook, Johanna I

2018-05-04

To examine variation in pressure injury (PI) incidence among long-term aged care facilities and identify resident- and facility-level factors that explain this variation. Longitudinal incidence study using routinely-collected electronic care management data. A large aged care service provider in New South Wales and the Australian Capital Territory, Australia. About 6556 people aged 65 years and older who were permanent residents in 60 long-term care facilities between December 2014 and November 2016. Risk-adjusted PI incidence rates over eight study quarters. Incidence density over the study period was 1.33 pressure injuries per 1000 resident days (95% confidence interval (CI) = 1.29-1.37). Funnel plots were used to identify variation among facilities. On average, 14% of facilities had risk-adjusted PI rates that were higher than expected in each quarter (above 95% funnel plot control limits). Ten percent of facilities had persistently high rates in any three or more consecutive quarters (n = 6). The variation between facilities was only partly explained by resident characteristics in multilevel regression models. Residents were more likely to have higher-pressure injury rates in facilities in regional areas compared with major city areas (adjusted incidence rate ratio = 1.25, 95% CI = 1.04-1.51), and facilities with persistently high rates were more likely to be located in areas with low socioeconomic status (P = 0.038). There is considerable variation among facilities in PI incidence. This study demonstrates the potential of routinely-collected care management data to monitor PI incidence and to identify facilities that may benefit from targeted intervention.

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

International Nuclear Information System (INIS)

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

1995-01-01

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

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

International Nuclear Information System (INIS)

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

1995-10-01

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

Geothermal direct-heat utilization assistance. Quarterly project progress report, July 1996--September 1996. Federal Assistance Program

Energy Technology Data Exchange (ETDEWEB)

Lienau, P.

1996-11-01

This report summarizes geothermal technical assistance, R&D and technology transfer activities of the Geo-Heat Center at Oregon Institute of Technology for the fourth quarter of FY-96. It describes 152 contacts with parties during this period related to technical assistance with geothermal direct heat projects. Areas dealt with include geothermal heat pumps, space heating, greenhouses, aquaculture, equipment, economics and resources. Research activities are summarized on greenhouse peaking. Outreach activities include the publication of a geothermal direct use Bulletin, dissemination of information, geothermal library, technical papers and seminars, and progress monitor reports on geothermal resources and utilization.

Environmental surveillance data report for the third quarter of 1987

International Nuclear Information System (INIS)

Daniels, K.L.; Goldberg, P.Y.; Horwedel, B.M.; McCollough, I.L.; Osborne-Lee, A.E.; Owenby, R.K.; Watson, J.B.; Wilson, M.M.

1987-12-01

During the third quarter of 1987, over 1600 samples which represent more than 5000 analyses and measurements were collected by the Environmental Monitoring and Compliance (EMC) Department. Uranium concentrations measured on air filters near the Y-12 plant were higher than normal due to a release from that facility in May. More than 60% of the noncompliances with the NPDES permit for the third quarter occurred in July. These were primarily in total suspended solids at the Sewage Treatment Plant. The cause of these high concentrations has been explored with the plant operating staff but is currently unresolved. Because of past noncompliances in fecal coliform and chlorine concentrations at the Sewage Treatment Plant, an engineering review has been initiated to examine the present chlorination system. This review is intended to provide a permanent solution to these types of problems. Maximum concentrations of total radioactive strontium ( 89 Sr + 90 Sr) in bluegill were lower than those measured during the second quarter. There were not significant differences in the total radioactive strontium in blue gill at any of the Clinch River locations. 17 figs., 45 tabs

The AMTEX Partnership. Third quarterly report, FY 1995

Energy Technology Data Exchange (ETDEWEB)

Lemon, D.K.; Quisenberry, R.K. [AMTEX Partnership (United States)

1995-06-01

Key activities for the quarter were the initiation of tactical work on the OPCon Project, development of a draft of the AMTEX Policies and Procedures document, and a meeting of the Industry Technical Advisory Committee. A significant milestone was reached when a memorandum of understanding was signed between the DOE and The Department of Commerce. The agreement signified the official participation of the National Institute of Standards and Technology on the Demand Activated Manufacturing Architecture (DAMA) project in AMTEX. Project accomplishments are given for: computer-aided manufacturing, cotton biotechnology, DAMA, electronic embedded fingerprints, rapid cutting, sensors for agile manufacturing, and textile resource conservation.

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 31, 1956

Energy Technology Data Exchange (ETDEWEB)

NA, NA [ORNL

1957-03-12

This quarterly progress report of the Aircraft Nuclear Propulsion Project at ORNL records the technical progress of research on circulating-fuel reactors and other ANP research at the Laboratory. The report is divided into five major parts: 1) Aircraft Reactor Engineering, 2) Chemistry, and 3) Metallurgy, 4) Heat Transfer and Physical Properties, Radiation Damage, and Fuel Recovery and Reprocessing, and 5) Reactor Shielding.

Low-level liquid radioactive waste treatment at Murmansk, Russia: Technical design and review of facility upgrade and expansion

International Nuclear Information System (INIS)

Dyer, R.S.; Diamante, J.M.

1996-07-01

The governments of Norway and the US have committed their mutual cooperation and support the Murmansk Shipping Company (MSCo) to expand and upgrade the Low-Level Liquid Radioactive Waste (LLRW) treatment system located at the facilities of the Russian company RTP Atomflot, in Murmansk, Russia. RTP Atomflot provides support services to the Russian icebreaker fleet operated by the MSCo. The objective is to enable Russia to permanently cease disposing of this waste in Arctic waters. The proposed modifications will increase the facility's capacity from 1,200 m 3 per year to 5,000 m 3 per year, will permit the facility to process high-salt wastes from the Russian Navy's Northern fleet, and will improve the stabilization and interim storage of the processed wastes. The three countries set up a cooperative review of the evolving design information, conducted by a joint US and Norwegian technical team from April through December, 1995. To ensure that US and Norwegian funds produce a final facility which will meet the objectives, this report documents the design as described by Atomflot and the Russian business organization, ASPECT, both in design documents and orally. During the detailed review process, many questions were generated, and many design details developed which are outlined here. The design is based on the adsorption of radionuclides on selected inorganic resins, and desalination and concentration using electromembranes. The US/Norwegian technical team reviewed the available information and recommended that the construction commence; they also recommended that a monitoring program for facility performance be instituted

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-04-01

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

Technical Merits and Leadership in Facility Management

National Research Council Canada - National Science Library

Shoemaker, Jerry

1997-01-01

.... The document is divided into six chapters; the introduction, facility management and leadership, building systems, facility operations, facility maintenance strategies, and the conclusion and final analysis...

Staff technical position on regulatory considerations in the design and construction of the exploratory shaft facility

International Nuclear Information System (INIS)

Gupta, D.; Peshel, J.; Bunting, J.

1991-07-01

The staff of the US Nuclear Regulatory Commission has prepared this staff technical position for the purpose of compiling and further clarifying previous staff positions on regulatory considerations in the design and construction of the exploratory shaft facility (ESF). (The US Department of Energy (DOE) now refers to the ESF as the ''exploratory studies facility.'' DOE's change in terminology does not affect the positions taken in this guidance.) This document lists the key regulations in 10 CFR Part 60 that should be considered in the design and construction of the ESF and presents the staff position statements and corresponding discussions. 13 refs., 1 fig

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.

Tampa electric company - IGCC project. Quarterly report, January 1, 1996--March 31, 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-02-01

This quarterly report consists of materials presented at a recent review of the project. The project is an IGCC project being conducted by Tampa Electric Company. The report describes the status of the facility construction, components, operations staff training, and discusses aspects of the project which may impact the final scheduled completion.

Short-term energy outlook: Quarterly projections, Third quarter 1992

International Nuclear Information System (INIS)

1992-08-01

The Energy Information Administration (EIA) prepares quarterly, short-term energy supply, demand, and price projections for publication in February, May, August, and November in the Short-Term Energy Outlook (Outlook). An annual supplement analyzes the performance of previous forecasts, compares recent cases with those of other forecasting services, and discusses current topics related to the short-term energy markets. (See Short-Term Energy Outlook Annual Supplement, DOE/EIA-0202.) The principal users of the Outlook are managers and energy analysts in private industry and government. The forecast period for this issue of the Outlook extends from the third quarter of 1992 through the fourth quarter of 1993. Values for the second quarter of 1992, however, are preliminary EIA estimates (for example, some monthly values for petroleum supply and disposition are derived in part from weekly data reported in the Weekly Petroleum Status Report) or are calculated from model simulations using the latest exogenous information available (for example, electricity sales and generation are simulated using actual weather data). The historical energy data are EIA data published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications. Minor discrepancies between the data in these publications and the historical data in this Outlook are due to independent rounding

Short-term energy outlook, quarterly projections, first quarter 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-01-01

The forecast period for this issue of the Outlook extends from the first quarter of 1998 through the fourth quarter of 1999. Values for the fourth quarter of 1997, however, are preliminary EIA estimates (for example, some monthly values for petroleum supply and disposition are derived in part from weekly data reported in EIA`s Weekly Petroleum Status Report) or are calculated from model simulations that use the latest exogenous information available (for example, electricity sales and generation are simulated by using actual weather data). The historical energy data, compiled in the first quarter 1998 version of the Short-Term Integrated Forecasting System (STIFS) database, are mostly EIA data regularly published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications. Minor discrepancies between the data in these publications and the historical data in this Outlook are due to independent rounding. The STIFS model is driven principally by three sets of assumptions or inputs: estimates of key macroeconomic variables, world oil price assumptions, and assumptions about the severity of weather. Macroeconomic estimates are adjusted by EIA to reflect EIA assumptions which may affect the macroeconomic outlook. By varying the assumptions, alternative cases are produced by using the STIFS model. 24 figs., 19 tabs.

Quarterly coal report, July--September 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-02-01

The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks. Coke production consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for July through September 1997 and aggregated quarterly historical data for 1991 through the second quarter of 1997. Appendix A displays, from 1991 on, detailed quarterly historical coal imports data. 72 tabs.

Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Working Material

International Nuclear Information System (INIS)

2013-01-01

In recent years, engineering oriented work, rather than basic research and development (R&D), has led to significant progress in improving the economics of innovative fast reactors and associated fuel cycle facilities, while maintaining and even enhancing the safety features of these systems. Optimization of plant size and layout, more compact designs, reduction of the amount of plant materials and the building volumes, higher operating temperatures to attain higher generating efficiencies, improvement of load factor, extended core lifetimes, high fuel burnup, etc. are good examples of achievements to date that have improved the economics of fast neutron systems. The IAEA, through its Technical Working Group on Fast Reactors (TWG-FR) and Technical Working Group on Nuclear Fuel Cycle Options and Spent Fuel Management (TWG-NFCO), devotes many of its initiatives to encouraging technical cooperation and promoting common research and technology development projects among Member States with fast reactor and advanced fuel cycle development programmes, with the general aim of catalysing and accelerating technology advances in these fields. In particular the theme of fast reactor deployment, scenarios and economics has been largely debated during the recent IAEA International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, held in Paris in March 2013. Several papers presented at this conference discussed the economics of fast reactors from different national and regional perspectives, including business cases, investment scenarios, funding mechanisms and design options that offer significant capital and energy production cost reductions. This Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics addresses Member States’ expressed need for information exchange in the field, with the aim of identifying the main open issues and launching possible initiatives to help and

Quarterly coal report, April--June 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-11-01

The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience. Coke production, consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for April through June 1997 and aggregated quarterly historical data for 1991 through the first quarter of 1997. Appendix A displays, from 1991 on, detailed quarterly historical coal imports data. Appendix B gives selected quarterly tables converted to metric tons. To provide a complete picture of coal supply and demand in the US, historical information has been integrated in this report. 8 figs., 73 tabs.

Eighth experts meeting on environmental radioactivity monitoring: Technical and organisational means for an optimised measurement of ambient radioactivity in the environment of nuclear facilities

International Nuclear Information System (INIS)

1991-01-01

The plant-specific emission monitoring and environmental monitoring near nuclear facilities are part of the items of the agreement between the EC and the IAEA, for mutual rapid information in the case of accidents. The lectures presented to the technical discussion meeting deal with the legal and technical aspects involved. Dispersion models, computer-aided dispersion models, computer-aided information systems and advanced programs as well as measuring techniques and results of the emission monitoring and environmental monitoring near nuclear facilities are the aspects of main interest discussed at the meeting. (DG) [de

32 CFR 643.127 - Quarters.

Science.gov (United States)

2010-07-01

... Additional Authority of Commanders § 643.127 Quarters. The assignment and rental of quarters to civilian employees and other nonmilitary personnel will be accomplished in accordance with AR 210-50. Responsibility of the Corps of Engineers for the establishment of rental rates for quarters rented to civilian and...

Metallurgical Laboratory Hazardous Waste Management Facility groundwater monitoring report

International Nuclear Information System (INIS)

Thompson, C.Y.

1993-03-01

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

Geothermal direct-heat utilization assistance: Federal assistance program. Quarterly project progress report, October--December 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-02-01

The report summarizes geothermal technical assistance, R&D and technology transfer activities of the Geo-Heat Center at Oregon Institute of Technology for the first quarter of FY-96. It describes 90 contacts with parties during this period related to technical assistance with geothermal direct heat projects. Areas dealt with include geothermal heat pumps, space heating, greenhouses, aquaculture, equipment and resources. Research activities are summarized on low-temperature resource assessment, geothermal district heating system cost evaluation and silica waste utilization project. Outreach activities include the publication of a geothermal direct use Bulletin, dissemination of information, geothermal library, technical papers and seminars, development of a webpage, and progress monitor reports on geothermal resources and utilization.

Quarter 9 Mercury information clearinghouse final report

Energy Technology Data Exchange (ETDEWEB)

Laudal, D.L.; Miller, S.; Pflughoeft-Hassett, D.; Ralston, N.; Dunham, G.; Weber, G.

2005-12-15

The Canadian Electricity Association (CEA) identified a need and contracted the Energy & Environmental Research Center (EERC) to create and maintain an information clearinghouse on global research and development activities related to mercury emissions from coal-fired electric utilities. A total of eight reports were completed and are summarized and updated in this final CEA quarterly report. Selected topics were discussed in detail in each quarterly report. Issues related to mercury from coal-fired utilities include the general areas of measurement, control, policy, and transformations. Specific topics that have been addressed in previous quarterly reports include the following: Quarterly 1 - Sorbent Control Technologies for Mercury Control; Quarterly 2 - Mercury Measurement; Quarterly 3 - Advanced and Developmental Mercury Control Technologies; Quarterly 4 - Prerelease of Mercury from Coal Combustion By-Products; Quarterly 5 - Mercury Fundamentals; Quarterly 6 - Mercury Control Field Demonstrations; Quarterly 7 - Mercury Regulations in the United States: Federal and State; and Quarterly 8 - Commercialization Aspects of Sorbent Injection Technologies in Canada. In this last of nine quarterly reports, an update of these mercury issues is presented that includes a summary of each topic, with recent information pertinent to advances made since the quarterly reports were originally presented. In addition to a comprehensive update of previous mercury-related topics, a review of results from the CEA Mercury Program is provided. 86 refs., 11 figs., 8 tabs.

An overview of technical requirements on durable concrete production for near surface disposal facilities for radioactive wastes

International Nuclear Information System (INIS)

Tolentino, Evandro; Tello, Cledola Cassia Oliveira de

2013-01-01

Radioactive waste can be generated by a wide range of activities varying from activities in hospitals to nuclear power plants, to mines and mineral processing facilities. General public have devoted nowadays considerable attention to the subject of radioactive waste management due to heightened awareness of environmental protection. The preferred strategy for the management of all radioactive waste is to contain it and to isolate it from the accessible biosphere. The Federal Government of Brazil has announced the construction for the year of 2014 and operation for the year of 2016 of a near surface disposal facility for low and intermediate level radioactive waste. The objective of this paper is to provide an overview of technical requirements related to production of durable concrete to be used in near surface disposal facilities for radioactive waste concrete structures. These requirements have been considered by researchers dealing with ongoing designing effort of the Brazilian near surface disposal facility. (author)

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

Energy Technology Data Exchange (ETDEWEB)

A. David Lester

2008-10-17

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

Lead Coolant Test Facility Technical and Functional Requirements, Conceptual Design, Cost and Construction Schedule

International Nuclear Information System (INIS)

Soli T. Khericha

2006-01-01

This report presents preliminary technical and functional requirements (T and FR), thermal hydraulic design and cost estimate for a lead coolant test facility. The purpose of this small scale facility is to simulate lead coolant fast reactor (LFR) coolant flow in an open lattice geometry core using seven electrical rods and liquid lead or lead-bismuth eutectic. Based on review of current world lead or lead-bismuth test facilities and research need listed in the Generation IV Roadmap, five broad areas of requirements of basis are identified: Develop and Demonstrate Prototype Lead/Lead-Bismuth Liquid Metal Flow Loop Develop and Demonstrate Feasibility of Submerged Heat Exchanger Develop and Demonstrate Open-lattice Flow in Electrically Heated Core Develop and Demonstrate Chemistry Control Demonstrate Safe Operation and Provision for Future Testing. These five broad areas are divided into twenty-one (21) specific requirements ranging from coolant temperature to design lifetime. An overview of project engineering requirements, design requirements, QA and environmental requirements are also presented. The purpose of this T and FRs is to focus the lead fast reactor community domestically on the requirements for the next unique state of the art test facility. The facility thermal hydraulic design is based on the maximum simulated core power using seven electrical heater rods of 420 kW; average linear heat generation rate of 300 W/cm. The core inlet temperature for liquid lead or Pb/Bi eutectic is 420 C. The design includes approximately seventy-five data measurements such as pressure, temperature, and flow rates. The preliminary estimated cost of construction of the facility is $3.7M. It is also estimated that the facility will require two years to be constructed and ready for operation

Quarterly coal report, April--June, 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-11-01

The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for April through June 1998 and aggregated quarterly historical data for 1992 through the first quarter of 1998. Appendix A displays, from 1992 on, detailed quarterly historical coal imports data. 58 tabs.

Quarterly coal report, October--December 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for October through December 1998 and aggregated quarterly historical data for 1992 through the third quarter of 1998. Appendix A displays, from 1992 on, detailed quarterly historical coal imports data. 58 tabs.

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.

Natural Gas Imports and Exports. Third Quarter Report 1999

International Nuclear Information System (INIS)

1999-01-01

The second quarter 1997 Quarterly Report of Natural Gas Imports and Exports featured a Quarterly Focus report on cross-border natural gas trade between the United States and Mexico. This Quarterly Focus article is a follow-up to the 1997 report. This report revisits and updates the status of some of the pipeline projects discussed in 1997, and examines a number of other planned cross-border pipeline facilities which were proposed subsequent to our 1997 report. A few of the existing and proposed pipelines are bidirectional and thus have the capability of serving either Mexico, or the United States, depending on market conditions and gas supply availability. These new projects, if completed, would greatly enhance the pipeline infrastructure on the U.S.-Mexico border and would increase gas pipeline throughput capacity for cross-border trade by more than 1 billion cubic feet (Bcf) per day. The Quarterly Focus is comprised of five sections. Section I includes the introduction as well as a brief historic overview of U.S./Mexican natural gas trade; a discussion of Mexico's energy regulatory structure; and a review of trade agreements and a 1992 legislative change which allows for her cross-border gas trade in North America. Section II looks at initiatives that have been taken by the Mexican Government since 1995to open its energy markets to greater competition and privatization. Section III reviews Mexican gas demand forecasts and looks at future opportunities for U.S. gas producers to supplement Mexico's indigenous supplies in order to meet the anticipated rapid growth in demand. Section IV examines the U.S.-Mexico natural gas trade in recent years. It also looks specifically at monthly import and export volumes and prices and identifies short-term trends in this trade. Finally, Section V reviews the existing and planned cross-border gas pipeline infrastructure. The section also specifically describes six planned pipelines intended to expand this pipeline network and

Natural Gas Imports and Exports. Third Quarter Report 1999

Energy Technology Data Exchange (ETDEWEB)

none

1999-10-01

The second quarter 1997 Quarterly Report of Natural Gas Imports and Exports featured a Quarterly Focus report on cross-border natural gas trade between the United States and Mexico. This Quarterly Focus article is a follow-up to the 1997 report. This report revisits and updates the status of some of the pipeline projects discussed in 1997, and examines a number of other planned cross-border pipeline facilities which were proposed subsequent to our 1997 report. A few of the existing and proposed pipelines are bidirectional and thus have the capability of serving either Mexico, or the United States, depending on market conditions and gas supply availability. These new projects, if completed, would greatly enhance the pipeline infrastructure on the U.S.-Mexico border and would increase gas pipeline throughput capacity for cross-border trade by more than 1 billion cubic feet (Bcf) per day. The Quarterly Focus is comprised of five sections. Section I includes the introduction as well as a brief historic overview of U.S./Mexican natural gas trade; a discussion of Mexico's energy regulatory structure; and a review of trade agreements and a 1992 legislative change which allows for her cross-border gas trade in North America. Section II looks at initiatives that have been taken by the Mexican Government since 1995to open its energy markets to greater competition and privatization. Section III reviews Mexican gas demand forecasts and looks at future opportunities for U.S. gas producers to supplement Mexico's indigenous supplies in order to meet the anticipated rapid growth in demand. Section IV examines the U.S.-Mexico natural gas trade in recent years. It also looks specifically at monthly import and export volumes and prices and identifies short-term trends in this trade. Finally, Section V reviews the existing and planned cross-border gas pipeline infrastructure. The section also specifically describes six planned pipelines intended to expand this pipeline

High Exposure Facility Technical Description

Energy Technology Data Exchange (ETDEWEB)

Carter, Gregory L.; Stithem, Arthur R.; Murphy, Mark K.; Smith, Alex K.

2008-02-12

The High Exposure Facility is a collimated high-level gamma irradiator that is located in the basement of the 318 building. It was custom developed by PNNL back in 1982 to meet the needs for high range radiological instrument calibrations and dosimeter irradiations. At the time no commercially available product existed that could create exposure rates up to 20,000 R/h. This document is intended to pass on the design criteria that was employed to create this unique facility, while maintaining compliance with ANSI N543-1974, "General Safety Standard for Installations Using Non-Medical X-Ray and Sealed Gamma-Ray Sources, Energies up to 10 MeV."

The AMTEX Partnership. Third quarter report

Energy Technology Data Exchange (ETDEWEB)

1994-06-01

The AMTEX Partnership is a collaborative research and development program among the U.S. Integrated Textile Industry, the Department of Energy, The DOE laboratories, other federal agencies and laboratories, and universities. The goal of AMTEX is to strengthen the competitiveness of this vital U.S. industry and thereby preserve and create American jobs. During the third quarter of 1994 all the Cooperative Research and Development Agreements (CRADAs) were completed and work initiated for three additional projects: Computer Aided Fabric Evaluation (CAFE), Textile Resource Conservation (TReC), and Sensors for Agile Manufacturing (SFAM). The plan for a Cotton Biotechnology project was completed and reviewed by the Industry Technical Advisory Committee. In addition, an `impact study` on the topic of flexible fiber production was conducted by an industry group led by the fiber manufacturers.

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.

Quarterly coal report, January--March 1993

Energy Technology Data Exchange (ETDEWEB)

1993-08-20

The United States produced 242 million short tons of coal in the first quarter of 1993, a decrease of 6 percent (14 million short tons) from the amount produced during the first quarter of 1992. The decrease was due to a decline in production east of the Mississippi River. All major coal-producing States in this region had lower coal production levels led by West Virginia, which produced 5 million short tons less coal. The principal reasons for the overall drop in coal output compared to a year earlier were: A decrease in demand for US coal in foreign markets; a slower rate of producer/distributor stock build-up; and a drawn-down of electric utility coal stocks. Distribution of US coal in the first quarter of 1993 was 10 million short tons lower than in the first quarter of 1992, with 5 million short tons less distributed to both electric utilities and overseas markets. The average price of coal delivered to electric utilities during the first quarter of 1993 was $28.65 per short ton, the lowest value since the first quarter of 1980. Coal consumption in the first quarter of 1993 was 230 million short tons, 4 percent higher than in the first quarter of 1992, due primarily to a 5-percent increase in consumption at electric utility plants. Total consumer stocks, at 153 million short tons, and electric utility stocks, at 144 million short tons, were at their lowest quarterly level since the end of 1989. US. coal exports totaled 19 million short tons, 6 million short tons less than in the first quarter of 1992, and the lowest quarterly level since 1988. The decline was primarily due to a 1-million-short-ton drop in exports to each of the following destinations: Italy, France, Belgium and Luxembourg, and Canada.

Quarterly coal report, January--March 1993

International Nuclear Information System (INIS)

1993-01-01

The United States produced 242 million short tons of coal in the first quarter of 1993, a decrease of 6 percent (14 million short tons) from the amount produced during the first quarter of 1992. The decrease was due to a decline in production east of the Mississippi River. All major coal-producing States in this region had lower coal production levels led by West Virginia, which produced 5 million short tons less coal. The principal reasons for the overall drop in coal output compared to a year earlier were: A decrease in demand for US coal in foreign markets; a slower rate of producer/distributor stock build-up; and a drawn-down of electric utility coal stocks. Distribution of US coal in the first quarter of 1993 was 10 million short tons lower than in the first quarter of 1992, with 5 million short tons less distributed to both electric utilities and overseas markets. The average price of coal delivered to electric utilities during the first quarter of 1993 was $28.65 per short ton, the lowest value since the first quarter of 1980. Coal consumption in the first quarter of 1993 was 230 million short tons, 4 percent higher than in the first quarter of 1992, due primarily to a 5-percent increase in consumption at electric utility plants. Total consumer stocks, at 153 million short tons, and electric utility stocks, at 144 million short tons, were at their lowest quarterly level since the end of 1989. US. coal exports totaled 19 million short tons, 6 million short tons less than in the first quarter of 1992, and the lowest quarterly level since 1988. The decline was primarily due to a 1-million-short-ton drop in exports to each of the following destinations: Italy, France, Belgium and Luxembourg, and Canada

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

Energy Technology Data Exchange (ETDEWEB)

Pettersen, Finn Erik Ljaastad; Eliston, Anton Jayanand; Vaeringstad, Thomas; Lund, Per Tore Jensen; Magnussen, Ingrid; Langseth, Benedicte; Willumsen, Mats Oeivind; Rasmussen, Kristian; Guren, Ingri

2012-07-01

Second quarter of 2012 was cold. Total inflow was 47.0 TWh, 8.8 TWh less than normal. At the end of the quarter, the reservoir level 68.4 percent. It is 1.8 percentage points above normal for time of year and 1.2 percentage points higher than the same time last year. Norway had a power consumption of 28.2 TWh in the second quarter, which is 4.2 percent higher than in the same quarter last year. The last 12 months the consumption have been 125.7 TWh, compared with 128.7 TWh the preceding 12 months. The power production in Norway was 33.3 TWh in the second quarter - an increase of 26.1 percent compared with the same quarter last year. The last 12 months the Norwegian production has been 145.8 TWh, compared with 120.9 TWh the preceding 12 months. The production increase is due to that the last year has been much wetter than the preceding. This has also given high export abroad. In the second quarter Norway had a net export of 5.1 TWh, compared with a net import of 0.6 TWh in the second quarter last year. The good resource gave a low price level in the wholesale market for electricity. On average for the second quarter was the average spot price in West, Southwest and Eastern Norway, 201, 202 and 203 Nok / MWh. In Central and Northern Norway, the average price 218 and 213 Nok/ MWh. (eb)

Temporal Changes in Technical and Physical Performances During a Small-Sided Game in Elite Youth Soccer Players.

Science.gov (United States)

Moreira, Alexandre; Saldanha Aoki, Marcelo; Carling, Chris; Alan Rodrigues Lopes, Rafael; Felipe Schultz de Arruda, Ademir; Lima, Marcelo; Cesar Correa, Umberto; Bradley, Paul S

2016-12-01

There have been claims that small-sided games (SSG) may generate an appropriate environment to develop youth players' technical performance associated to game-related problem solving. However, the temporal change in technical performance parameters of youth players during SSG is still unknown. The aim of this study was to examine temporal changes in technical and physical performances during a small-sided game (SSG) in elite soccer players. Sixty elite youth players (age 14.8 ± 0.2 yr; stature 177 ± 5 cm; body mass 66.2 ± 4.7 kg) completed a 5 v 5 SSG using two repetitions of 8 minutes interspersed by 3 minutes of passive recovery. To evaluate temporal changes in performance, the data were analysed across 4 minutes quarters. Physical performance parameters included the total distance covered (TDC), the frequency of sprints (>18 km•h -1 ), accelerations and decelerations (> 2.0 m•s -2 and - 2.0 m•s -2 ), metabolic power (W•kg -1 ), training impulse (TRIMP), TDC: TRIMP, number of impacts, and body load. Technical performance parameters included goal attempts, total number of tackles, tackles and interceptions, total number of passes, and passes effectiveness. All physical performance parameters decreased from the first to the last quarter with notable declines in TDC, metabolic power and the frequency of sprints, accelerations and decelerations (P performance parameters did not vary across quarters (P > 0.05; trivial ES for 1st v 4th quarters: 0.15 - 0.33). The data demonstrate that technical performance is maintained despite substantial declines in physical performance during a SSG in elite youth players. This finding may have implications for designing SSG's for elite youth players to ensure physical, technical and tactical capabilities are optimized. Modifications in player number, pitch dimensions, rules, coach encouragement, for instance, should be included taking into account the main aim of a given session and then focused on overloading physical or

F-Area Seepage Basins groundwater monitoring report, fourth quarter 1991 and 1991 summary

International Nuclear Information System (INIS)

1992-03-01

This progress report for fourth quarter 1991 and 1991 summary fro the Savannah River Plant includes discussion on the following topics: description of facilities; hydrostratigraphic units; monitoring well nomenclature; integrity of the monitoring well network; groundwater monitoring data; analytical results exceeding standards; tritium, nitrate, and pH time-trend data; water levels; groundwater flow rates and directions; upgradient versus downgradient results

Low Energy Accelerator Laboratory Technical Area 53, Los Alamos National Laboratory. Environmental assessment

International Nuclear Information System (INIS)

1995-04-01

This Environmental Assessment (EA) analyzes the potential environmental impacts that would be expected to occur if the Department of Energy (DOE) were to construct and operate a small research and development laboratory building at Technical Area (TA) 53 at the Los Alamos National Laboratory (LANL), Los Alamos, New Mexico. DOE proposes to construct a small building to be called the Low Energy Accelerator Laboratory (LEAL), at a previously cleared, bladed, and leveled quarter-acre site next to other facilities housing linear accelerator research activities at TA-53. Operations proposed for LEAL would consist of bench-scale research, development, and testing of the initial section of linear particle accelerators. This initial section consists of various components that are collectively called an injector system. The anticipated life span of the proposed development program would be about 15 years

Joint Force Quarterly. Issue 41, 2nd Quarter, April 2006

Science.gov (United States)

2006-04-01

companies participated, a million more people would be actively looking for threats. Aguas de Amazonas, a subsidiary of Suez Environnement, a...9 Richard B. Myers, “A Word from the Chair- man,” Joint Force Quarterly 37 (2d Quarter 2005), 5. 10 Wald, 26. 11 “Suez— Aguas de Amazonas Water for...humanitarian duties. They have overseen over 130 humani- tarian projects worth in excess of $7.6 million and ranging from a medical center, to potable

Identification of Vital Areas at Nuclear Facilities. Technical Guidance

International Nuclear Information System (INIS)

2012-01-01

The possibility that nuclear or other radioactive material could be used for malicious purposes cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material and to effectively respond to nuclear security events. States have agreed to strengthen existing and established new international legal instruments to enhance nuclear security around the world. Nuclear security is fundamental in the management of nuclear technologies and in applications where nuclear or other radioactive material is used or transported. Through its nuclear security programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in such material; national response plans; and contingency measures. With its nuclear security series, the IAEA aims to assist States to implement and sustain such a regime in a coherent and integrated manner. The IAEA Nuclear Security Series comprises: Nuclear Security Fundamentals, which include objectives and essential elements of a State?s nuclear security regime; Recommendations; Implementing Guides; and Technical Guidance publications. Each State carries the full responsibility for nuclear security, i.e. to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; and to combat illicit trafficking and the inadvertent movement of such material. It should also be prepared to respond to a nuclear security event. The IAEA recommendations for the protection of

Quarterly coal report, January--March 1998

Energy Technology Data Exchange (ETDEWEB)

Young, P.

1998-08-01

The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for January through March 1998 and aggregated quarterly historical data for 1992 through the fourth quarter of 1997. Appendix A displays, from 1992 on, detailed quarterly historical coal imports data. To provide a complete picture of coal supply and demand in the United States, historical information has been integrated in this report. 58 tabs.

Quarterly coal report, October--December 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-05-01

The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for October through December 1996 and aggregated quarterly historical data for 1990 through the third quarter of 1996. Appendix A displays, from 1988 on, detailed quarterly historical coal imports data. To provide a complete picture of coal supply and demand in the US, historical information has been integrated in this report. 8 figs., 72 tabs.

Quarterly coal report, July--September 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-02-01

The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for July through September 1998 and aggregated quarterly historical data for 1992 through the second quarter of 1998. 58 tabs.

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-07-01

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

Quarterly report for the electricity market. 1. quarter of 2012; Kvartalsrapport for kraftmarknaden. 1. kvartal 2012

Energy Technology Data Exchange (ETDEWEB)

Pettersen, Finn Erik Ljaastad; Eliston, Anton Jaynanand; Guren, Ingri; Homqvist, Erik; Lund, Per Tore Jensen; Magnussen, Ingrid; Rasmussen, Kristian; Ulriksen, Margit Iren

2012-07-01

The first quarter of 2012 was unusually mild and wetter than normal. Total inflow was 16.8 TWh, 7.5 TWh more than normal. This ensured a high reservoir levels and at the end of the quarter the filling was 50.5 percent. It is 12.5 percentage points over the normal for the time of year and 32.4 percentage points higher than the same time last year. Norway had a power consumption of 37.5 TWh in the first quarter, which is 2.3 percent less than in the same quarter last year. the past 12 months, consumption has been 124.2 TWh, compared with 129.7 TWh the preceding 12 months. Power production in Norway was 42.3 TWh in the first quarter - an increase of 32.3 percent compared with the same quarter last year. The last 12 months have the Norwegian production been 138.5 TWh compared to 117.7 TWh the the previous 12 months. The production increase is due to milder and wetter weather than normal over the past year. This involvement also high the exports abroad. In the first quarter, Norway had a net export of 4.8 TWh, compared with a net import of 6.4 TWh in the first quarter last year. The good resource, combined with a low consumption gave a low price level in wholesale market for electricity. On average for the fourth quarter was the average spot price in the South and West Norway, Nok 272 and 275 / MWh. In Eastern Norway, the average price of Nok 283 / MWh, while it was Nok 285 / MWh in the Middle and Northern Norway. (Author)

Geothermal direct-heat utilization assistance. Federal Assistance Program quarterly project progress report, April 1--June 30, 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

This report summarizes geothermal technical assistance, R and D and technology transfer activities of the Geo-Heat Center at Oregon Institute of Technology for the third quarter of FY98 (April--June, 1998). It describes 231 contacts with parties during this period related to technical assistance with geothermal direct heat projects. Areas dealt with included requests for general information including material for high school and university students, and material on geothermal heat pumps, resource and well data, spacing heating and cooling, greenhouses, aquaculture, equipment, district heating, resorts and spas, industrial applications, snow melting and electric power. Research activities include work on model construction specifications for line shaft submersible pumps and plate heat exchangers, and a comprehensive aquaculture developers package. A brochure on Geothermal Energy in Klamath County was developed for state and local tourism use. Outreach activities include the publication of the Quarterly Bulletin (Vol. 19, No. 2) with articles on research at the Geo-Heat Center, sustainability of geothermal resources, injection well drilling in Boise, ID and a greenhouse project in the Azores. Other outreach activities include dissemination of information mainly through mailings of publications, tours of local geothermal uses, geothermal library acquisitions and use, participation in workshops, short courses and technical meetings by the staff, and progress monitor reports on geothermal activities.

Development of technical design for waste processing and storage facilities for Novi Han repository

International Nuclear Information System (INIS)

Canizares, J.; Benitez, J.C.; Asuar, O.; Yordanova, O.; Demireva, E.; Stefanova, I.

2005-01-01

Empresarion Agrupados Internacional S.A. (Spain) and ENPRO Consult Ltd. (Bulgaria) were awarded a contract by the Central Finance and Contracts Unit to develop the technical design of the waste processing and storage facilities at the Novi Han repository. At present conceptual design phase is finished. This conceptual design covers the definition of the basic design requirements to be applied to the installations defined above, following both European and Bulgarian legislation. In this paper the following items are considered: 1) Basic criteria for the layout and sizing of buildings; 2) Processing of radioactive waste, including: treatment and conditioning of disused sealed sources; treatment of liquid radioactive wastes; treatment of solid radioactive waste; conditioning of liquid and solid radioactive waste; 3) Control of waste packages and 4) Storage of radioactive waste, including storage facility and waste packages. An analysis of inventories of stored and estimated future wastes and its subsequent processes is also presented and the waste streams are illustrated

[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.

Hydroacoustic Studies Using HydroCAM - Station-centric Integration of Models and Observations. Quarterly Report No. 5 October - December 2003

International Nuclear Information System (INIS)

Upton, Zachary M.; Pulli, Jay J.

2004-01-01

OAK-B135 Quarterly Technical Report summarizing BBN's support of the DOE/NNSA GNEM program. This report details BBN's efforts to improve the modeling of explosions and other events underwater and their propagation to hydroacoustic sensor networks. OK to release, no restriction on copyright

Technical Merits and Leadership in Facility Management

National Research Council Canada - National Science Library

Shoemaker, Jerry

1997-01-01

After almost ten years of experience and formal education in design, construction, and facility operations and maintenance, the challenges and complexity of facility management still seem overwhelming and intangible...

Inertial confinement fusion. Quarterly report, July--September 1995, Volume 5, Number 4

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

The 1990 National Academy of Sciences (NAS) final report recommended proceeding with the construction of a 1- to 2-MJ Nd-doped glass laser designed to achieve ignition in the laboratory (a laser originally called the Nova Upgrade, but now called the National Ignition Facility, or NIF, and envisioned as a national user facility). As a prerequisite, the report recommended completion of a series of target physics objectives on the Nova laser in use at the Lawrence Livermore National Laboratory (LLNL). Meeting these objectives, which were called the Nova Technical Contract (NTC), would demonstrate (the Academy committee believed) that the physics of ignition targets was understood well enough that the laser requirements could be accurately specified. Completion of the NTC objectives was given the highest priority in the NAS report. The NAS committee also recommended a concentrated effort on advanced target design for ignition. As recommended in the report, completion of these objectives has been the joint responsibility of LLNL and the Los Alamos National Laboratory. Most of the articles in this issue of the ICF Quarterly were written jointly by scientists from both institutions. Several of the NTC objectives required the completion of improvements to Nova`s power balance and pointing accuracy and of new diagnostics and new target fabrication capabilities. These improvements were called {open_quotes}Precision Nova{close_quotes} and are documented. The original NTC objectives have been largely met. This Introduction summarizes those objectives and their motivation in the context of the requirements for ignition. The articles that follow describe the NIF ignition target designs and summarize the principal accomplishments in the various elements of the NTC.

Minutes of the IFMIF technical meetings, May 17-20, 2005, Tokyo, Japan

International Nuclear Information System (INIS)

Ida, Mizuho; Nakamura, Hiroo; Yutani, Toshiaki; Maebara, Sunao; Umetsu, Tomotake; Sugimoto, Masayoshi

2005-08-01

The International Fusion Materials Irradiation Facility (IFMIF) Technical Meetings were held on May 17-20, 2005 at Japan Atomic Energy Research Institute (JAERI) Tokyo. The main objectives were 1) to review technical status of the subsystems; accelerator, target and test facilities, 2) to technically discuss interface issues between target and test facilities, 3) to review results of peer-reviews performed in the EU and Japan, 4) to harmonize design/experimental activities among the subsystems, 5) to review and discuss the Engineering Validation and Engineering Design Activity (EVEDA) tasks, and 6) to make a report of 1) - 5) to the IFMIF Executive Subcommittee. This report presents a brief summary of the Target Technical, Meeting, Test Facilities Technical Meeting, Target/Test Facilities Interface Meeting, Accelerator Technical Meeting and the Technical Integration Meeting. (author)

ARM Climate Research Facility Quarterly Ingest Status Report

Energy Technology Data Exchange (ETDEWEB)

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

2016-10-01

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

ARM Climate Research Facility Quarterly Ingest Status Report

Energy Technology Data Exchange (ETDEWEB)

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

2016-07-01

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

Quarterly coal report, January--March 1994

Energy Technology Data Exchange (ETDEWEB)

1994-08-24

The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. The data presented in the QCR are collected and published by the Energy Information Administration (EIA) to fulfill data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275), as amended. This report presents detailed quarterly data for January through March 1994 and aggregated quarterly historical data for 1986 through the fourth quarter of 1993. Appendix A displays, from 1986 on, detailed quarterly historical coal imports data, as specified in Section 202 of the Energy Policy and Conservation Amendments Act of 1985 (Public Law 99-58). Appendix B gives selected quarterly tables converted to metric tons.

Quarterly coal report, October--December 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-05-01

The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. The data presented in the QCR are collected and published by the Energy Information Administration (EIA) to fulfill data collection and dissemination responsibilities. This report presents detailed quarterly data for october through December 1997 and aggregated quarterly historical data for 1991 through the third quarter of 1997. Appendix A displays, from 1991 on, detailed quarterly historical coal imports data, as specified in Section 202 of the energy Policy and Conservation Amendments Act of 1985 (Public Law 99-58). Appendix B gives selected quarterly tables converted to metric tons. To provide a complete picture of coal supply and demand in the US, historical information has been integrated in this report. 8 figs., 73 tabs.

Quarterly coal report, January--March 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-08-01

This Quarterly Coal Report (QCR) provides comprehensive information about U.S. coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience,including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. The data presented in the QCR are collected and published by the Energy Information Administration (EIA) to fulfill data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275), as amended. This report presents detailed quarterly data for January through March 1997 and aggregated quarterly historical data for 1991 through the fourth quarter of 1996. Appendix A displays, from 1988 on, detailed quarterly historical coal imports data, as specified in Section 202 of the Energy Policy and Conservation Amendments Act of 1985 (Public Law 99-58). Appendix B gives selected quarterly tables converted to metric tons.

340 Facility emergency preparedness hazards assessment

International Nuclear Information System (INIS)

Campbell, L.R.

1998-01-01

This document establishes the technical basis in support of Emergency Planning activities for the 340 Facility on the Hanford Site. Through this document, the technical basis for the development of facility specific Emergency Action Levels and Emergency Planning Zone, is demonstrated

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

Energy Technology Data Exchange (ETDEWEB)

Voyles, JW

2011-01-17

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

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...

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).

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.

Mixed Waste Management Facility (MWMF) groundwater monitoring report

International Nuclear Information System (INIS)

1993-06-01

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

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

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

Quarterly financial reports | IDRC - International Development ...

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

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

Quarterly report of RCRA groundwater monitoring data for period April 1 through June 30, 1994

International Nuclear Information System (INIS)

1994-10-01

Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs as defined in the Resource Conservation and Recovery Act of 1976 (RCRA); and ''Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilities,'' as amended (40 Code of Federal Regulations [CFR] 265). Compliance with the 40 CFR 265 regulations is required by the Washington Administrative Code (WAC) 173-303. This report contains data from Hanford Site groundwater monitoring projects. Westinghouse Hanford Company manages RCRA groundwater monitoring projects for federal facilities on the Hanford Site. Project management, specifying data needs, performing quality control oversight, managing data, and preparing project sampling schedules are all parts of this responsibility. This quarterly report contains data received between May 20 and August 19, 1994, which are the cutoff dates for this reporting period. This report may contain not only data from the April through June quarter but also data from earlier sampling events that were not previously reported

methodological and technical aspects to be considered in the location of physical recreational sports facilities

Directory of Open Access Journals (Sweden)

Jesús I. Benítez Llanes

2012-03-01

Full Text Available Sometimes we wonder. Why practitioners of recreational physical activities do not make systematic use of a particular sports facility ?, Why some sports facility remains almost always empty? Why it is continued unnecessarily reversed large sums of material resources for maintenance? For the simple reason that sports facilities were from the beginning that were not well conceived and designed architecturally, where among other things, not sporting habits and population size of the place properly examined. Similarly, we have witnessed criteria issued regarding the performance of a specific sports field, far from contributing to the extension and improvement of the practice of recreational physical and sports activities in its various manifestations, its null or poor continuous maintenance contributing negatively to limit the sporting life and lacerate mental and physical welfare of the inhabitants of the environment. Justifications that led the author of this research to the development of methodological technical aspects regarding the location of recreational physical sports infrastructure, content which also form part of the subject and / or curricular unit "Spaces and Sports Facilities" currently teaches future professionals and managers of Physical Culture for the last two academic years at the University of the Sciences of Physical Culture and Sport Nancy Uranga Romagoza in Pinar del Río Cuba and the Iberoamerican University of Sport in Venezuela.

Results for the second quarter 2014 tank 50 WAC slurry sample chemical and radionuclide contaminants

International Nuclear Information System (INIS)

Bannochie, C.

2014-01-01

This report details the chemical and radionuclide contaminant results for the characterization of the 2014 Second Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC) in effect at that time. Information from this characterization will be used by DWPF & Saltstone Facility Engineering (DSFE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System

Results for the Third Quarter 2014 Tank 50 WAC slurry sample: Chemical and radionuclide contaminants

Energy Technology Data Exchange (ETDEWEB)

Crawford, Charles L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2015-01-08

This report details the chemical and radionuclide contaminant results for the characterization of the 2014 Third Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC) in effect at that time.¹ Information from this characterization will be used by DWPF & Saltstone Facility Engineering (DSFE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System.

Results For The Fourth Quarter 2014 Tank 50 WAC Slurry Sample: Chemical And Radionuclide Contaminants

Energy Technology Data Exchange (ETDEWEB)

Crawford, C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2015-09-30

This report details the chemical and radionuclide contaminant results for the characterization of the Calendar Year (CY) 2014 Fourth Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC) in effect at that time. Information from this characterization will be used by DWPF & Saltstone Facility Engineering (DSFE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System.

Results For The Second Quarter 2013 Tank 50 WAC Slurry Sample: Chemical And Radionuclide Contaminants

Energy Technology Data Exchange (ETDEWEB)

Bannochie, Christopher J.

2013-07-31

This report details the chemical and radionuclide contaminant results for the characterization of the 2013 Second Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC) in effect at that time. Information from this characterization will be used by Saltstone Facility Engineering (SFE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System.

Report to Congress on abnormal occurrences, July--September 1977. Quarterly report

International Nuclear Information System (INIS)

1977-11-01

Section 208 of the Energy Reorganization Act of 1974 identifies an abnormal occurrence as an unscheduled incident or event which the Nuclear Regulatory Commission determines to be significant from the standpoint of public health or safety and requires a quarterly report of such events to be made to Congress. This report, the tenth in the series, covers the period July 1 to September 30, 1977. The NRC has determined that during this period there were no abnormal occurrences at the 65 nuclear power plants licensed to operate nor at fuel cycle facilities. There was one abnormal occurrence at other licensee facilities, which involved the loss and recovery of a radioactive source and probable overexposure. This report also contains information updating previously reported abnormal occurrences

Regulatory and technical reports (abstract index journal): Annual compilation for 1987

International Nuclear Information System (INIS)

1988-03-01

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

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.

Development of Integral Effect Test Facility P and ID and Technical Specification for SMART Fluid System

International Nuclear Information System (INIS)

Lee, Sang Il; Jung, Y. H.; Yang, H. J.; Song, S. Y.; Han, O. J.; Lee, B. J.; Kim, Y. A.; Lim, J. H.; Park, K. W.; Kim, N. G.

2010-01-01

SMART integral test loop is the thermal hydraulic test facility with a high pressure and temperature for simulating the major systems of the prototype reactor, SMART-330. The objective of this project is to conduct the basic design for constructing SMART ITL. The major results of this project include a series of design documents, technical specifications and P and ID. The results can be used as the fundamental materials for making the detailed design which is essential for manufacturing and installing SMART ITL

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.

An ecological quarter in Neuchatel, Switzerland. Phase 3: two new educational facilities; Deux ecoles pour le quartier Ecoparc. En quete d'harmonie durable

Energy Technology Data Exchange (ETDEWEB)

Schafer, L.

2009-07-01

This richly illustrated article reports on the phase 3 of the construction of an ecological quarter in the city of Neuchatel, Switzerland. In this urban area of 4 hectares, new buildings are replacing former industrial buildings. The architects and the city authorities put the emphasis on energy conservation and efficiency, together with ecological considerations and modern appropriate architecture. The area is located near the city railway station and includes (i) the Swiss Federal Office of Statistics, (ii) eight residential buildings, (iii) two educational facilities for 1700 students and (iv) one commercial and office building. The article is focused on phase 3 and is supplemented by an interview of the principal architect. The two educational facilities - a music academy and a business school - are located in a single 193 m long building adjacent to the railway tracks. Synergies have been used to create common rooms like library and concert/conference hall. Highly efficient artificial lighting has been developed with the appliances' manufacturer. Dessicant cooling is used to cool the large rooms of the building. Heat is provided for cooling, space heating and hot water by wood chips boilers. There is plenty of wood available from the surrounding forests, which are insufficiently renewed so far. In the interview the architect explains how a compromise was found between ecological requirements and investment cost, leading to a sustainable development of the area.

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.

Mirror fusion. Quarterly report, April-June 1981

Energy Technology Data Exchange (ETDEWEB)

1981-09-11

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

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

Energy Technology Data Exchange (ETDEWEB)

Cooper, J.T.

1998-10-01

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

LFCM [liquid-fed ceramic melter] vitrification technology: Quarterly progress report, January--March 1987

International Nuclear Information System (INIS)

Brouns, R. A.; Allen, C. R.; Powell, J. A.

1988-05-01

This report is compiled by the Nuclear Waste Treatment Program and the Hanford Waste Vitrification Program at Pacific Northwest Laboratory to describe the progress in developing, testing, applying and documenting liquid-fed ceramic melter vitrification technology. Progress in the following technical subject areas during the second quarter of FY 1987 is discussed: melting process chemistry and glass development, feed preparation and transfer systems, melter systems, canister filling and handling systems, and process/product modeling. 23 refs., 14 figs., 10 tabs

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.)

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)

Lessons Learned from Independent Technical Reviews of U.S. Department of Energy Low-Level Radioactive Waste Landfills/Disposal Facilities

International Nuclear Information System (INIS)

Adams, V.; Gupta, D.C.; Smegal, J.S.

2009-01-01

This paper describes the lessons learned from a series of independent technical reviews (ITRs) of waste management operations conducted at existing and proposed low-level radioactive waste landfills/disposal facilities at U.S. Department of Energy (DOE) sites. The evaluated waste disposal programs include those at Hanford, Idaho, Savannah River Site, Oak Ridge, Portsmouth, Paducah, and the Nevada Test Site. Based on these evaluations, cost-effective lessons learned were identified to improve reliability and effectiveness of DOE on-site disposal facilities. Key recommendations covered a wide range of issues, including the following: complex-wide applied research effort is needed to evaluate settlement behavior of DOE wastes and how they may affect cover performance; there is a need for unbiased assessment of relevance of liners for different climates and wastes to evaluate where and when liners should be used; there is a need to develop information to demonstrate attenuation capability of modern liner materials and to understand the attenuation capability of liners during performance assessment; a review of historical data on demolition volumes and logistics from past DOE projects can provide valuable insight that can be helpful in planning capacity of future on-site disposal facilities; and operating procedures need to be reviewed and updated on a regular basis so that procedures remain consistent with changes in requirements and take advantage of improvements in technology. The complex-wide independent reviews have assisted DOE sites in considering lessons learned regarding common technical, regulatory, and management issues. Facility management and their operating contractors have begun implementing the applicable recommendations within the context of the DOE Order 435.1, Radioactive Waste Management. (authors)

Confinement Physics Research Facility/ZTH: A progress report

International Nuclear Information System (INIS)

Hammer, C.F.; Thullen, P.

1989-01-01

In October 1985 the Los Alamos National Laboratory's Controlled Thermonuclear Research (CTR) Division began the design and construction of the Confinement Physics Research Facility (CPRF) and the ZTH toroidal, reversed-field-pinch (RFP), plasma physics experiment. The CPRF is a facility which will provide the buildings, utilities, pulsed power system, control system and diagnostics needed to operate a magnetically confined fusion experiment, and ZTH will be the first experiment operated in the facility. The construction of CPRF/ZTH is scheduled for completion in the first quarter of 1993. 5 figs

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-31

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

Quarterly report of RCRA groundwater monitoring data for period January 1--March 31, 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

This quarterly report contains data received between January and March 1995, which are the cutoff dates for this reporting period. This report may contain not only data from the January through March quarter, but also data from earlier sampling events that were not previously reported. Nineteen Resource Conservation and Recovery Act of 1976 (RCRA) groundwater monitoring projects are conducted at the Hanford Site. These projects include treatment, storage, and disposal facilities for both solid and liquid waste. The groundwater monitoring programs described in this report comply with the interim-status federal (Title 40 Code of Federal Regulation [CFR] Part 265) and state (Washington Administrative Code [WAC] 173-303-400) regulations. The RCRA projects are monitored under one of three programs: background monitoring, indicator parameter evaluation, or groundwater quality assessment.

Third-quarter 1989 electric utility financial results

International Nuclear Information System (INIS)

Studness, C.M.

1990-01-01

Utility earnings per share before write-offs fell 6.9% in the third quarter of 1989 from the year-earlier level. Write-offs reduced third-quarter earnings of a sample of 83 utilities that account for 95% of investor-owned utility revenue by $792 million, compared with $183 million in the year-earlier quarter. With larger write-offs in 1989 than in 1988, third-quarter earnings per share after write-offs plunged 16.9% from the year-earlier level

Nuclear Energy Center Site Survey, 1975. Part III. Technical considerations

International Nuclear Information System (INIS)

1976-01-01

Studies of the technical feasibility of nuclear energy centers (NECs) and the comparison between NEC technical feasibility and that of nuclear facilities on dispersed sites are reviewed. The conclusions related to technical feasibility of NEC are summarized. Technical feasibility was found to rest mainly on five major issues: heat dissipation, transmission, facility construction, radiological impact, and environmental impact. Although general conclusions can be reached in these five areas, it is recognized that they are interdependent, and detailed site-by-site analysis will be necessary. Some general conclusions on technical feasibility of NECs are presented, then detailed conclusions derived from the technical evaluation of NECs compared to dispersed site facilities are presented. The findings of this study on each of the five major feasibility issues are then discussed in sequence. The study concludes that nuclear energy centers, as defined herein, are technically feasible

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.)

ARM Climate Research Facility Quarterly Value-Added Product Report

Energy Technology Data Exchange (ETDEWEB)

Sivaraman, Chitra

2014-01-14

The purpose of this report is to provide a concise status update for value-added products (VAP) implemented by the Atmospheric Radiation Measurement Climate Research Facility. The report is divided into the following sections: (1) new VAPs for which development has begun, (2) progress on existing VAPs, (3) future VAPs that have been recently approved, (4) other work that leads to a VAP, and (5) top requested VAPs from the archive.

Quarterly coal report July--September 1996, February 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-02-01

The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for July through September 1996 and aggregated quarterly historical data for 1990 through the second quarter of 1996. Appendix A displays, from 1988 on, detailed quarterly historical coal imports data. 8 figs., 72 tabs.

Mixed Waste Management Facility (MWMF) groundwater monitoring report

International Nuclear Information System (INIS)

1993-03-01

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

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.)

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.).

Technical and economic feasibility study for the reactivation of the integral test facility of IPEN/CNEN Nuclear Engineering Center

Energy Technology Data Exchange (ETDEWEB)

Biaty, Flávia P.; Rocha, Marcelo da S.; Oliveira, Otávio L. de, E-mail: flavia.biaty@usp.br, E-mail: msrocha@ipen.br, E-mail: otavioluis@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

2017-07-01

The Integral Test Facility of Nuclear Engineering Center (CEN/IPEN/CNEN-SP), known as 'Loop 70', is a semi-industrial thermal-hydraulic test facility and can operate as a BWR (Boiling Water Reactor) or a PWR (Pressurizing Water Reactor) mode. Designed and built in the 1980's, it is currently disabled. The experimental circuits ('test loop') are facilities that reproduce the thermohydraulic and fluid dynamic conditions that occur inside a reactor and are used to simulate the practical reality which it is not possible to be obtained through mathematical models. In this context, this research project aims the development of a Business Plan to analyze the technical and economic feasibility related to the reactivation of the facility. This methodology (adapted to the government sector) is a decision-making tool that will offer a wide perspective of the project, set the guidelines and actions that will define the future of the facility and provide a general rule to make investments on it. This paper presents the historic aspects to better understand the Loop 70's current situation. It also presents information about similar facilities around the world, services that can be offered (thermal-hydraulics parameters measurements, equipment qualification and transient analysis due accident situations), results of the strategic analysis (SWOT) performed, specific goals for each critical success or failure factor of the facility, financial aspects related to the reactivation and an overview of the facility's perspectives. (author)

Technical and economic feasibility study for the reactivation of the integral test facility of IPEN/CNEN Nuclear Engineering Center

International Nuclear Information System (INIS)

Biaty, Flávia P.; Rocha, Marcelo da S.; Oliveira, Otávio L. de

2017-01-01

The Integral Test Facility of Nuclear Engineering Center (CEN/IPEN/CNEN-SP), known as 'Loop 70', is a semi-industrial thermal-hydraulic test facility and can operate as a BWR (Boiling Water Reactor) or a PWR (Pressurizing Water Reactor) mode. Designed and built in the 1980's, it is currently disabled. The experimental circuits ('test loop') are facilities that reproduce the thermohydraulic and fluid dynamic conditions that occur inside a reactor and are used to simulate the practical reality which it is not possible to be obtained through mathematical models. In this context, this research project aims the development of a Business Plan to analyze the technical and economic feasibility related to the reactivation of the facility. This methodology (adapted to the government sector) is a decision-making tool that will offer a wide perspective of the project, set the guidelines and actions that will define the future of the facility and provide a general rule to make investments on it. This paper presents the historic aspects to better understand the Loop 70's current situation. It also presents information about similar facilities around the world, services that can be offered (thermal-hydraulics parameters measurements, equipment qualification and transient analysis due accident situations), results of the strategic analysis (SWOT) performed, specific goals for each critical success or failure factor of the facility, financial aspects related to the reactivation and an overview of the facility's perspectives. (author)

Performance specifications for proton medical facility

Energy Technology Data Exchange (ETDEWEB)

Chu, W.T.; Staples, J.W.; Ludewigt, B.A.; Renner, T.R.; Singh, R.P.; Nyman, M.A.; Collier, J.M.; Daftari, I.K.; Petti, P.L.; Alonso, J.R. [Lawrence Berkeley Lab., CA (United States); Kubo, H.; Verhey, L.J. [University of California Davis Medical Center, Sacramento, CA (United States). Cancer Center]|[California Univ., San Francisco, CA (United States). School of Medicine; Castro, J.R. [Lawrence Berkeley Lab., CA (United States)]|[University of California Davis Medical Center, Sacramento, CA (United States). Cancer Center]|[California Univ., San Francisco, CA (United States). School of Medicine

1993-03-01

Performance specifications of technical components of a modern proton radiotherapy facility are presented. The technical items specified include: the accelerator; the beam transport system including rotating gantry; the treatment beamline systems including beam scattering, beam scanning, and dosimetric instrumentation; and an integrated treatment and accelerator control system. Also included are treatment ancillary facilities such as diagnostic tools, patient positioning and alignment devices, and treatment planning systems. The facility specified will accommodate beam scanning enabling the three-dimensional conformal therapy deliver .

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.

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.

Technical study gas storage. Final report

International Nuclear Information System (INIS)

Borowka, J.; Moeller, A.; Zander, W.; Koischwitz, M.A.

2001-01-01

This study will answer the following questions: (a) For what uses was the storage facility designed and for what use is it currently applied? Provide an overview of the technical data per gas storage facility: for instance, what is its capacity, volume, start-up time, etc.; (b) How often has this facility been used during the past 10 years? With what purpose was the facility brought into operation at the time? How much gas was supplied at the time from the storage facility?; (c) Given the characteristics and the use of the storage facility during the past 10 years and projected gas consumption in the future, how will the storage facility be used in the future?; (d) Are there other uses for which the gas storage facility can be deployed, or can a single facility be deployed for numerous uses? What are the technical possibilities in such cases? Questions (a) and (b) are answered separately for every storage facility. Questions (c) and (d) in a single chapter each (Chapter 2 and 3). An overview of the relevant storage data relating to current use, use in the last 10 years and use in future is given in the Annex

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.

Quarterly, Bi-annual and Annual Reports

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — The Quarterly, Bi-annual and Annual Reports are periodic reports issued for public release. For the deep set fishery these reports are issued quarterly and anually....

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.)

Fast flux test facility hazards assessment

International Nuclear Information System (INIS)

Sutton, L.N.

1994-01-01

This document establishes the technical basis in support of Emergency Planning Activities for the Fast Flux Test Facility on the Hanford Site. The document represents an acceptable interpretation of the implementing guidance document for DOE Order 5500.3A. Through this document, the technical basis for the development of facility specific Emergency Action Levels and the Emergency Planning Zone is demonstrated

Decree of the Czech Labor Safety Office No. 263/1991 amending the Decree No. 76/1989 on ensuring safety of technical facilities in the nuclear power sector

International Nuclear Information System (INIS)

1995-01-01

Some provisions of the Decree of the Czech Labor Safety Office No. 76/1989 on ensuring safety of technical facilities in the nuclear power sector are amended, particularly in the field of construction activities, assembling, reconstruction and repair of nuclear power facilities. The Decree entered into force on 28 June 1991. (J.B.)

MCO loading and cask loadout technical manual

International Nuclear Information System (INIS)

PRAGA, A.N.

1998-01-01

A compilation of the technical basis for loading a multi-canister overpack (MCO) with spent nuclear fuel and then placing the MCO into a cask for shipment to the Cold Vacuum Drying Facility. The technical basis includes a description of the process, process technology that forms the basis for loading alternatives, process control considerations, safety considerations, equipment description, and a brief facility structure description

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

Energy Technology Data Exchange (ETDEWEB)

Cooper, J.T.

1998-10-01

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

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.)

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.).

Quarterly Environmental Radiological Survey Summary Third Quarter 1998, 100, 200, 300, and 600 Areas; TOPICAL

International Nuclear Information System (INIS)

MCKINNEY, S.M.

1998-01-01

This report provides a summary of the radiological surveys performed in support of near-facility environmental monitoring at the Hanford Site. The Third Quarter 1998 survey results and the status of actions required are summarized: (1) All of the eighty-five environmental radiological surveys scheduled during July, August and September were performed as planned. Fifty-one of the surveys were conducted at Project Hanford Management Contractors (PHMC) sites and thirty-four at Environmental Restoration Contractor (ERC) sites. Contamination above background levels was found at seventeen of the PHMC waste sites and two of the ERC waste sites. Contamination levels as high and gt;1,000,000 disintegrations per minute (dpm) per 100 cm(sup 2) were reported. Of these contaminated surveys nine were in Underground Radioactive Material (URM) areas, three were in unposted areas and seven were in contamination areas. The contamination found within four of the URM and three of the CA areas was immediately cleaned up and no further action was required. The remaining five URM and two unposted sites were posted and along with the five CA sites will require remediation. Radiological Problem Reports (RPR's) were issued and the sites were turned over to the landlord for further action as required. (2) During the second quarter of 1998, 1.2 hectares (3.0 acres) were stabilized and radiologically down posted from Contamination Area (CA)/Soil Contamination (SC) to URM. (3) Four hectares (10 acres) located south and west of B-Plant were posted as a radiological buffer area as a result of a contamination spread. This off-normal occurrence is currently being investigated. (4) Four Surveillance Compliance Inspection Reports (SCIRs) remained open and had not been resolved. Tank Farms Operations has responsibility for the unresolved SCIRs

Third quarter 2005 sales figures; Chiffre d'affaires du 3. trimestre 2005

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

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

300 Area fuel supply shutdown facility hazards assessment

International Nuclear Information System (INIS)

Campbell, L.R.

1998-01-01

This document establishes the technical basis in support of Emergency Planning activities for the 300 Area Fuel Supply Shutdown Facilities on the Hanford Site. Through this document, the technical basis for the development of facility specific Emergency Action Levels and Emergency Planning Zone, is demonstrated

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.)

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.).

Oak Ridge Reservation Federal Facility Agreement for the Environmental Restoration Program. Volume 4

International Nuclear Information System (INIS)

1993-10-01

This quarterly progress report satisfies requirements for the Environmental Restoration (ER) Program that are specified in the Oak Ridge Reservation (ORR) Federal Facility Agreement (FFA) established between the U.S. Department of Energy (DOE), the U.S. Environmental protection Agency (EPA), and the Tennessee Department of Environment and Conservation (TDEC). The reporting period covered is July through September 1993 (fourth quarter of FY 1993). Sections 1.1 and 1.2 provide respectively the milestones scheduled for completion during the reporting period and a list of documents that have been proposed for transmittal during the following quarter but have not been approved as FY 1994 commitments

Annual Report for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2016

Energy Technology Data Exchange (ETDEWEB)

Birdsell, Kay Hanson [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stauffer, Philip H. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Atchley, Adam Lee [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Miller, Elizabeth D. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Chu, Shaoping [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); French, Sean B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-03-24

As a condition to the disposal authorization statement issued to Los Alamos National Laboratory (LANL or the Laboratory) on March 17, 2010, a comprehensive performance assessment and composite analysis (PA/CA) maintenance program must be implemented for the Technical Area 54, Area G disposal facility. Annual determinations of the adequacy of the PA/CA are to be conducted under the maintenance program to ensure that the conclusions reached by those analyses continue to be valid. This report summarizes the results of the fiscal year (FY) 2016 annual review for Area G.

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.

NS&T Management Observations - 3rd Quarter

Energy Technology Data Exchange (ETDEWEB)

Gianotto, David [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-07-01

The INL Management Observation Program (MOP) is designed to improve managers and supervisors understanding of work being performed by employees and the barriers impacting their success. The MOP also increases workers understanding of managements’ expectations as they relate to safety, security, quality, and work performance. Management observations are designed to improve the relationship and trust between employees and managers through increased engagement and interactions between managers and researchers in the field. As part of continuous improvement, NS&T management took initiative to focus on the participation and quality of observations in FY 14. This quarterly report is intended to (a) summarize the participation and quality of management’s observations, (b) assess observations for commonalities or trends related to facility or process barriers impacting research, and (c) provide feedback and make recommendations for improvements NS&T’s MOP.

NS&T Management Observations: Quarterly Performance Analysis

Energy Technology Data Exchange (ETDEWEB)

Gianotto, David [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-09-01

The INL Management Observation Program (MOP) is designed to improve managers and supervisors understanding of work being performed by employees and the barriers impacting their success. The MOP also increases workers understanding of managements’ expectations as they relate to safety, security, quality, and work performance. Management observations (observations) are designed to improve the relationship and trust between employees and managers through increased engagement and interactions between managers and researchers in the field. As part of continuous improvement, NS&T management took initiative to focus on the participation and quality of observations in FY-14. This quarterly report is intended to (a) summarize the participation and quality of management’s observations, (b) assess observations for commonalities or trends related to facility or process barriers impacting research, and (c) provide feedback and make recommendations for improvements NS&T’s MOP.

NS&T Managment Observations - 1st Quarter

Energy Technology Data Exchange (ETDEWEB)

David Gianotto

2014-06-01

The INL Management Observation Program (MOP) is designed to improve managers and supervisors understanding of work being performed by employees and the barriers impacting their success. The MOP also increases workers understanding of managements’ expectations as they relate to safety, security, quality, and work performance. Management observations (observations) are designed to improve the relationship and trust between employees and managers through increased engagement and interactions between managers and researchers in the field. As part of continuous improvement, NS&T management took initiative to focus on the participation and quality of observations in FY 14. This quarterly report is intended to (a) summarize the participation and quality of management’s observations, (b) assess observations for commonalities or trends related to facility or process barriers impacting research, and (c) provide feedback and make recommendations for improvements NS&T’s MOP.

Patient Satisfaction in Military Dental Treatment Facilities

Science.gov (United States)

2006-03-07

the variance in regards to overall satisfaction. 15. SUBJECT TERMS Dentistry, Patient Satisfaction, Military, Consumer Satisfaction, Dental... patient satisfaction in military dental treatment facilities. Dental health is extremely important for the military as dental assets are not always... customer satisfaction is an important component of military dental care. Quarterly patient satisfaction reports are generated for each dental treatment

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)

Quarterly environmental radiological survey summary: Third quarter 1994--100, 200, 300, and 600 Areas

International Nuclear Information System (INIS)

McKinney, S.M.

1994-11-01

This report provides a summary of the radiological surveys performed on waste disposal sites located at the Hanford Site. The Third Quarter 1994 survey results and the status of actions required from current and past reports and are summarized below: (1) All the routine environmental radiological surveys scheduled during July, August, and September 1994 were completed except for the D Island vent riser area. The surveys for the 200-W railways, spurs, and sidings were completed during this period after being delayed by equipment problems during the second quarter. (2) No Compliance Assessment Reports (CARs) were issued for sites found out of compliance with standards identified in WHC-CM-7-5, Environmental Compliance. (3) Two Surveillance Compliance/Inspection Reports (SCIRs) were closed during the Third Quarter of 1994. (4) Eleven open SCIRs had not been resolved

Diagnostic development and support of MHD test facilities: Technical progress report for the period January, February, March 1985

International Nuclear Information System (INIS)

Shepard, W.S.; Cook, R.L.

1985-04-01

Mississippi State University is developing diagnostic instruments for MHD power train data acquisition and for support of MHD component development test facilities. Microprocessor-controlled optical instruments, initially developed for HRSR support, are being refined, and new systems to measure temperatures and gas-seed-slag stream characteristics are being developed. To further data acquisition and analysis capabilities, the diagnostic systems are being interfaced with MHD Energy Center computers. Additionally, technical support of the diagnostic needs of the national MHD research effort is being provided

Quarterly report of RCRA groundwater monitoring data for period January 1, 1993 through March 31, 1993

Energy Technology Data Exchange (ETDEWEB)

1993-07-01

Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs as defined in the Resource Conservation and Recovery Act of 1976 (RCRA); and Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilities, as amended (40 Code of Federal Regulations [CFR] 265). Compliance with the 40 CFR 265 regulations is required by the Washington Administrative Code (WAC) 173-303. This report contains data from Hanford Site groundwater monitoring projects. This quarterly report contains data received between March 8 and May 24, 1993, which are the cutoff dates for this reporting period. This report may contain not only data from the January through March quarter but also data from earlier sampling events that were not previously reported.

Catalogue and classification of technical safety standards, rules and regulations for nuclear power reactors and nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Fichtner, N.; Becker, K.; Bashir, M.

1977-01-01

The present report is an up-dated version of the report 'Catalogue and Classification of Technical Safety Rules for Light-water Reactors and Reprocessing Plants' edited under code No EUR 5362e, August 1975. Like the first version of the report, it constitutes a catalogue and classification of standards, rules and regulations on land-based nuclear power reactors and fuel cycle facilities. The reasons for the classification system used are given and discussed

Identification of Vital Areas at Nuclear Facilities. Technical Guidance (French Edition)

International Nuclear Information System (INIS)

2015-01-01

The possibility that nuclear or other radioactive material could be used for malicious purposes cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material and to effectively respond to nuclear security events. States have agreed to strengthen existing and established new international legal instruments to enhance nuclear security around the world. Nuclear security is fundamental in the management of nuclear technologies and in applications where nuclear or other radioactive material is used or transported. Through its nuclear security programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in such material; national response plans; and contingency measures. With its nuclear security series, the IAEA aims to assist States to implement and sustain such a regime in a coherent and integrated manner. The IAEA Nuclear Security Series comprises: Nuclear Security Fundamentals, which include objectives and essential elements of a State?s nuclear security regime; Recommendations; Implementing Guides; and Technical Guidance publications. Each State carries the full responsibility for nuclear security, i.e. to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; and to combat illicit trafficking and the inadvertent movement of such material. It should also be prepared to respond to a nuclear security event. The IAEA recommendations for the protection of

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.

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...

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

Quarterly coal report, January--March 1992

International Nuclear Information System (INIS)

Young, P.

1992-01-01

The United States produced 257 million short tons of coal in the first quarter of 1992. This was the second highest quarterly production level ever recorded. US coal exports in January through March of 1992 were 25 million short tons, the highest first quarter since 1982. The leading destinations for US coal exports were Japan, Italy, France, and the Netherlands, together receiving 46 percent of the total. Coal exports for the first quarter of 1992 were valued at $1 billion, based on an average price of $42.28 per short ton. Steam coal exports totaled 10 million short tons, an increase of 34 percent over the level a year earlier. Metallurgical coal exports amounted to 15 million short tons, about the same as a year earlier. US coal consumption for January through March 1992 was 221 million short tons, 2 million short tons more than a year earlier (Table 45). All sectors but the residential and commercial sector reported increased coal consumption

Observatory of electricity and gas markets, data from the 3. quarter 2004 to the 1. quarter 2013

International Nuclear Information System (INIS)

2013-04-01

This document gathers those published for each quarter since the 3. quarter 2004 and until the 1. quarter 2013. Each of them proposes and comments figures and tables of data regarding the electricity retail market (customer segments, evolution, price on the retail market), the electricity gross market (French market activity and European comparison, prices on the French market and European comparison, import and export volumes, market evolution), the gas retail market (customer segments, evolution, switch rate of providers, price, bill evolution...) and the gas gross market (price formation in France and in Europe, gross market activity in France, highlights)

A characterization and evaluation of coal liquefaction process streams. Quarterly report, April 1--June 30, 1997

Energy Technology Data Exchange (ETDEWEB)

Brandes, S.D.; Robbins, G.A.; Winschel, R.A.

1997-12-31

This is the Technical Progress Report for the twelfth quarter of activities. Described in this report are the following activities: (1) Thirty-nine samples from four run conditions of HTI Run PB-07 were received. Appropriate samples were characterized by proton NMR spectroscopy, Fourier transform infrared spectroscopy, vacuum distillation, and solvent quality tests. (2) The University of Delaware completed their subcontract this quarter. A meeting was held on April 30, 1997 at the University to close out the subcontract. (3) Twelve sets of samples were chosen from the CONSOL sample bank for the study of the insoluble and presumed unreactive material from process stream samples. Each set consists of the whole process stream and the 454 C{sup +} (850 F{sup +}) distillation resid derived from that process stream. Processing data for all samples were compiled. The samples represent four Wilsonville pilot plant runs and two HTI runs.

Technical bases for establishing a salt test facility

International Nuclear Information System (INIS)

1985-05-01

The need for a testing facility in which radioactive materials may be used in an underground salt environment is explored. No such facility is currently available in salt deposits in the United States. A salt test facility (STF) would demonstrate the feasibility of safely storing radioactive waste in salt and would provide data needed to support the design, construction, licensing, and operation of a radioactive waste repository in salt. Nineteen issues that could affect long-term isolation of waste materials in a salt repository are identified from the most pertinent recent literature. The issues are assigned an overall priority and a priority relative to the activities of the STF. Individual tests recommended for performance in the STF to resolve the 19 issues are described and organized under three groups: waste package performance, repository design and operation, and site characterization and evaluation. The requirements for a salt test facility are given in the form of functional criteria, and the approach that will be used in the design, execution, interpretation, and reporting of tests is discussed

Nigerian Quarterly Journal of Hospital Medicine: Submissions

African Journals Online (AJOL)

Nigerian Quarterly Journal of Hospital Medicine: Submissions. Journal Home > About the Journal > Nigerian Quarterly Journal of Hospital Medicine: Submissions. Log in or Register to get access to full text downloads.

Natural gas imports and exports. Second quarter report

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

The Office of Natural Gas and Petroleum Import and Export Activities prepares quarterly reports summarizing the data provided by companies authorized to import or export natural gas. Companies are required, as a condition of their authorizations, to file quarterly reports. This report is for the second quarter of 1997 (April through June).

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.

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.

Proposal on application of Russian technical facilities for International Mars Research Program for 2009 2015

Science.gov (United States)

Polishchuk, Georgy; Pichkhadze, Konstantin; Vorontsov, Victor; Pavel, Kazmerchuk

2006-07-01

Recently International Mars Research Program is widely discussed. Well-known initiative of President of the USA, recent progress of American and European scientists and engineers in implementation of “Mars Odyssey” and “Mars-Express” projects and Russian proposals on cooperation and participation in “Phobos Sample Return” mission declare every intention to join efforts in the ambitious Martian Program realization. The final goal of the program for nearly 15 20 years is landing of a man on the Martian surface. Before this event happens another critical stage will be Martian soil sample return. Within the next 10 years, apparently, a major task will be scale research by means of various types of technical facilities. A crucial issue for this research will be creation of research station network which would allow collecting information about planetary conditions at far-remote points. By this time within the frame of “Phobos Sample Return Program” to be launched in 2009 it is planned to deliver some meteorological mini-landers developed by the Russian and Finnish specialists on the Martian surface. From this point view it is also interesting to use balloons capable to cover considerable distance. Such proposals have been made by Russian side for “Scout” mission. European “Aurora” program also anticipates application of wide range of technical means to explore the Martian atmosphere and surface including inflatable devices. Thus, for the International Mars Exploration Program, it seems to be very prospective to use apart from launch vehicles, upper stages etc. such technical means as mini-stations, Mars rovers, penetrators, balloons, etc.

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.

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.)

Regulatory and technical reports (abstract index journal). Annual compilation for 1984. Volume 9, No. 4

International Nuclear Information System (INIS)

1985-01-01

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

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.

TECHNICAL BASIS DOCUMENT FOR NATURAL EVENT HAZARDS

International Nuclear Information System (INIS)

KRIPPS, L.J.

2006-01-01

This technical basis document was developed to support the documented safety analysis (DSA) and describes the risk binning process and the technical basis for assigning risk bins for natural event hazard (NEH)-initiated accidents. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the frequency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR-level controls

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.

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

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

Construction Management for Conventional Facilities of Proton Accelerator

International Nuclear Information System (INIS)

Kim, Jun Yeon; Cho, Jin Sam; Lee, Jae Sang

2008-05-01

Proton Engineering Frontier Project, puts its aim to building 100MeV 20mA linear proton accelerator which is national facility for NT, BT, IT, and future technologies, expected to boost up the national industry competitiveness. This R and D, Construction Management is in charge of the supportive works as site selection, architecture and engineering of conventional facilities, and overall construction management. The major goals of this work are as follows: At first, architecture and engineering of conventional facilities. Second, construction management, audit and inspection on construction of conventional facilities. Lastly, cooperation with the project host organization for adjusting technical issues of overall construction. In this research, We reviewed the basic design and made a detail design of conventional facilities. Preparation for construction license, site improvement and access road construction is fulfilled. Also, we made the technical support for project host as follows : selection of project host organization and host site selection, construction technical work for project host organization and procedure management

Technical basis document for natural event hazards

International Nuclear Information System (INIS)

CARSON, D.M.

2003-01-01

This technical basis document was developed to support the Tank Farms Documented Safety Analysis (DSA), and describes the risk binning process and the technical basis for assigning risk bins for natural event hazards (NEH)-initiated representative accident and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the frequency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR-level controls. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, ''Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'', as described in this report

Facility effluent monitoring plan determinations for the 200 Area facilities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-11-01

The following facility effluent monitoring plan determinations document the evaluations conducted for the Westinghouse Hanford Company 200 Area facilities (chemical processing, waste management, 222-S Laboratory, and laundry) on the Hanford Site in south central Washington State. These evaluations determined the need for facility effluent monitoring plans for the 200 Area facilities. The facility effluent monitoring plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438 (WHC 1991). The Plutonium/Uranium Extraction Plant and UO 3 facility effluent monitoring plan determinations were prepared by Los Alamos Technical Associates, Richland, Washington. The Plutonium Finishing Plant, Transuranic Waste Storage and Assay Facility, T Plant, Tank Farms, Low Level Burial Grounds, and 222-S Laboratory determinations were prepared by Science Applications International Corporation of Richland, Washington. The B Plant Facility Effluent Monitoring Plan Determination was prepared by ERCE Environmental Services of Richland, Washington

Animal facilities

International Nuclear Information System (INIS)

Fritz, T.E.; Angerman, J.M.; Keenan, W.G.; Linsley, J.G.; Poole, C.M.; Sallese, A.; Simkins, R.C.; Tolle, D.

1981-01-01

The animal facilities in the Division are described. They consist of kennels, animal rooms, service areas, and technical areas (examining rooms, operating rooms, pathology labs, x-ray rooms, and 60 Co exposure facilities). The computer support facility is also described. The advent of the Conversational Monitor System at Argonne has launched a new effort to set up conversational computing and graphics software for users. The existing LS-11 data acquisition systems have been further enhanced and expanded. The divisional radiation facilities include a number of gamma, neutron, and x-ray radiation sources with accompanying areas for related equipment. There are five 60 Co irradiation facilities; a research reactor, Janus, is a source for fission-spectrum neutrons; two other neutron sources in the Chicago area are also available to the staff for cell biology studies. The electron microscope facilities are also described

Hazardous materials in aquatic environments of the Mississippi River Basin. Quarterly progress report, July 1, 1995--September 30, 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

This report is the quarterly progress report for July through September 1995 for work done by Tulane and Xavier Universities under DOE contract number DE-FG01-93-EW53023. Accomplishments for various tasks including administrative activities, collaborative cluster projects, education projects, initiation projects, coordinated instrumentation facility, and an investigators` retreat are detailed in the report.

Ocean energy systems. Quarterly report, October-December 1982

Energy Technology Data Exchange (ETDEWEB)

1982-12-01

Research progress is reported on developing Ocean Thermal Energy Conversion (OTEC) systems that will provide synthetic fuels (e.g., methanol), energy-intensive products such as ammonia (for fertilizers and chemicals), and aluminum. The work also includes assessment and design concepts for hybrid plants, such as geothermal-OTEC (GEOTEC) plants. Another effort that began in the spring of 1982 is a technical advisory role to DOE with respect to their management of the conceptual design activity of the two industry teams that are designing offshore OTEC pilot plants that could deliver power to Oahu, Hawaii. In addition, a program is underway in which tests of a different kind of ocean-energy device, a turbine that is air-driven as a result of wave action in a chamber, are being planned. This Quarterly Report summarizes the work on the various tasks as of 31 December 1982.

Guide to good practices for the selection, training, and qualification of shift technical advisors

Energy Technology Data Exchange (ETDEWEB)

1993-02-01

The DOE Guide to Good Practices For The Selection, Training, and Qualification of Shift Technical Advisors can be used by any DOE nuclear facility that has implemented the shift technical advisor position. DOE Order 5480-20, ``Personnel Selection, Qualification, Training, and Staffing Requirements at DOE Reactor and Non-Reactor Nuclear Facilities,`` states that only Category A reactors must use shift technical advisor position. However, many DOE nuclear facilities have implemented the shift technical advisor position to provide independent on-shift technical advice and counsel to the shift operating personnel to help determine cause and mitigation of facility accidents. Those DOE nuclear facilities that have implemented or are going to implement the shift technical advisor position will find this guide useful. This guide addresses areas that may be covered by other training programs. In these cases, it is unnecessary (and undesirable) to duplicate these areas in the STA training program as long as the specific skills and knowledge essential for STAs are addressed. The guide is presented based on the premise that the trainee has not completed any facility-specific training other than general employee training.

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

Fourth-quarter Economic Growth and Time-varying Expected Returns

DEFF Research Database (Denmark)

Møller, Stig V.; Rangvid, Jesper

not predict returns. Fourth-quarter economic growth rates contain considerably more information about expected returns than standard variables used in the literature, are robust to the choice of macro variable, and work in-sample, out-of-sample, and in subsamples. To help explain these results, we show...... that economic growth and growth in consumer confidence are correlated during the fourth quarter, but not during the other quarters: When economic growth is low during the fourth quarter, confidence in the economy is also low such that investors require higher future returns. We discuss rational and behavioral...... reasons why fourth-quarter economic growth, growth in consumer confidence, and expected returns are related....

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.

Annual Report for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility – Fiscal Year 2015

Energy Technology Data Exchange (ETDEWEB)

French, Sean B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stauffer, Philip H. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Birdsell, Kay H. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-02-29

As a condition to the disposal authorization statement issued to Los Alamos National Laboratory (LANL or the Laboratory) on March 17, 2010, a comprehensive performance assessment and composite analysis maintenance program must be implemented for the Technical Area 54, Area G disposal facility. Annual determinations of the adequacy of the performance assessment and composite analysis (PA/CA) are to be conducted under the maintenance program to ensure that the conclusions reached by those analyses continue to be valid. This report summarizes the results of the fiscal year (FY) 2015 annual review for Area G.

Impact of Global Economic Crisis on Technical and Vocational ...

African Journals Online (AJOL)

The study examined the relationship between global economic crisis (GEC) and inadequacy of facilities for administration of the Technical and. Vocational Education. The descriptive survey design with a random sample of 100 technical teachers from a population of 139 technical teachers in all six Technical Colleges in ...

Estimation of optimal biomass fraction measuring cycle formunicipal solid waste incineration facilities in Korea.

Science.gov (United States)

Kang, Seongmin; Cha, Jae Hyung; Hong, Yoon-Jung; Lee, Daekyeom; Kim, Ki-Hyun; Jeon, Eui-Chan

2018-01-01

This study estimates the optimum sampling cycle using a statistical method for biomass fraction. More than ten samples were collected from each of the three municipal solid waste (MSW) facilities between June 2013 and March 2015 and the biomass fraction was analyzed. The analysis data were grouped into monthly, quarterly, semi-annual, and annual intervals and the optimum sampling cycle for the detection of the biomass fraction was estimated. Biomass fraction data did not show a normal distribution. Therefore, the non-parametric Kruskal-Wallis test was applied to compare the average values for each sample group. The Kruskal-Wallis test results showed that the average monthly, quarterly, semi-annual, and annual values for all three MSW incineration facilities were equal. Therefore, the biomass fraction at the MSW incineration facilities should be calculated on a yearly cycle which is the longest period of the temporal cycles tested. Copyright © 2017 Elsevier Ltd. All rights reserved.

Technical guide to criticality alarm system design

International Nuclear Information System (INIS)

Greenfield, B.

2009-01-01

An instructional manual was created to guide criticality safety engineers through the technical aspects of designing a criticality alarm system (CAS) for Dept. of Energy (DOE) hazard class 1 and 2 facilities. The manual was structured such that it can be used by engineers designing completely new systems and by those who are working with existing facilities. Major design tasks are thoroughly analyzed to provide concise direction for how to complete the analysis. Regulatory and technical performance requirements were both addressed. (authors)

FAIR - Baseline technical report. Executive summary

International Nuclear Information System (INIS)

Gutbrod, H.H.; Augustin, I.; Eickhoff, H.; Gross, K.D.; Henning, W.F.; Kraemer, D.; Walter, G.

2006-09-01

This document presents the Executive Summary, the first of six volumes comprising the 2006 Baseline Technical Report (BTR) for the international FAIR project (Facility for Antiproton and Ion Research). The BTR provides the technical description, cost, schedule, and assessments of risk for the proposed new facility. The purpose of the BTR is to provide a reliable basis for the construction, commissioning and operation of FAIR. The BTR is one of the central documents requested by the FAIR International Steering Committee (ISC) and its working groups, in order to prepare the legal process and the decisions on the construction and operation of FAIR in an international framework. It provides the technical basis for legal contracts on contributions to be made by, so far, 13 countries within the international FAIR Consortium. The BTR begins with this extended Executive Summary as Volume 1, which is also intended for use as a stand-alone document. The Executive Summary provides brief summaries of the accelerator facilities, the scientific programs and experimental stations, civil construction and safety, and of the workproject structure, costs and schedule. (orig.)

Evolving the US Army Research Laboratory (ARL) Technical Communication Strategy

Science.gov (United States)

2016-10-01

communication strategy. However, if the goal is to build support for Army S&T within the general public, then community outreach, mass media , and concise...Content into Popular Media 14 2.3 Leveraging Established S&T Audiences 15 3. Prong 2: Improve Workforce Technical and Strategic Communications Skills 16... community organization, STEM-related, activities (FIRST, Scouts, Citizen School), videos Permanent exhibit at a museum, quarterly for media

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.

77 FR 51705 - Rescission of Quarterly Financial Reporting Requirements

Science.gov (United States)

2012-08-27

... No. FMCSA-2012-0020] RIN-2126-AB48 Rescission of Quarterly Financial Reporting Requirements AGENCY...: FMCSA withdraws its June 27, 2012, direct final rule eliminating the quarterly financial reporting... future proposing the elimination of the quarterly financial reporting requirements for Form QFR and Form...

The ISOLDE facility

Science.gov (United States)

Catherall, R.; Andreazza, W.; Breitenfeldt, M.; Dorsival, A.; Focker, G. J.; Gharsa, T. P.; J, Giles T.; Grenard, J.-L.; Locci, F.; Martins, P.; Marzari, S.; Schipper, J.; Shornikov, A.; Stora, T.

2017-09-01

The ISOLDE facility has undergone numerous changes over the last 17 years driven by both the physics and technical community with a common goal to improve on beam variety, beam quality and safety. Improvements have been made in civil engineering and operational equipment while continuing developments aim to ensure operations following a potential increase in primary beam intensity and energy. This paper outlines the principal technical changes incurred at ISOLDE by building on a similar publication of the facility upgrades by Kugler (2000 Hyperfine Interact. 129 23-42). It also provides an insight into future perspectives through a brief summary issues addressed in the HIE-ISOLDE design study Catherall et al (2013 Nucl. Instrum. Methods Phys. Res. B 317 204-207).

The quarter wave resonator as a superconducting linac element

International Nuclear Information System (INIS)

Ben-Zvi, I.; Brennan, J.M.

1983-01-01

The electrical and mechanical properties of quarter wave resonators are derived. A procedure for optimal design of a quarter wave resonator for use in a superconducting heavy ion linac is given. It is concluded that a quarter wave resonator has significant advantages for this application. (orig.)

ARM Climate Research Facility Quarterly Value-Added Product Report

Energy Technology Data Exchange (ETDEWEB)

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

2016-10-01

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

Quarterly report of RCRA groundwater monitoring data for period October 1 through December 31, 1994

International Nuclear Information System (INIS)

1995-04-01

Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs as defined in the Resource Conservation and Recovery Act of 1976 (RCRA); and open-quotes Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilitiesclose quotes (Title 40 Code of Federal Regulations [CFR] Part 265), as amended. Compliance with the 40 CFR 265 regulations is required by the Washington Administrative Code (WAC) 173-303. This report contains data from Hanford Site groundwater monitoring projects. The location of each facility is shown. Westinghouse Hanford Company (WHC) manages the RCRA groundwater monitoring projects for federal facilities on the Hanford Site. Performing project management, preparing groundwater monitoring plans, well network design and installation, specifying groundwater data needs, performing quality control (QC) oversight, data management, and preparing project sampling schedules are all parts of this responsibility. Pacific Northwest Laboratory (PNL) administers the contract for analytical services and provides groundwater sampling services to WHC for the RCRA groundwater monitoring program. This quarterly report contains data received between October and December 1994, which are the cutoff dates for this reporting period. This report may contain not only data from the October through December quarter, but also data from earlier sampling events that were not previously reported

Is technical change directed by the supply of skills? The case of South Korea

NARCIS (Netherlands)

Serrano, L; Timmer, MP

In a recent contribution, Acemoglu [Quarterly Journal of Economics 113 (1998) 1055] modelled the effects of an increase in the supply of skills on the skill premium. We estimate a model to disentangle the short-run substitution effects and the effects of skill-biased technical change using industry

United States housing, second quarter 2013

Science.gov (United States)

Delton Alderman

2017-01-01

The U.S. housing market’s quarter two results were disap¬pointing compared with the first quarter. Although overall expected gains did not materialize, certain sectors improved slightly. Housing under construction, completions, and new and existing home sales exhibited slight increases. Overall permit data declined, and the decrease in starts was due primarily to a...

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.

(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.

Quarterly status of Department of Energy projects

International Nuclear Information System (INIS)

1982-01-01

This Quarterly Status of Department of Energy Projects is prepared by the Office of project and Facilities Management, MA-30. The report is designed to provide Department of Energy (DOE) management officials with a summary of the important baseline data that exists in the DOE project data base. This data base is maintained chiefly from periodic field management reports required by DOE Order 5700.4. Since most of the current estimates in this report are from field project managers, they do not necessarily have full Headquarters approval. The current budget data sheet estimates that appear in the report are considered appropriate for reporting external to the Department and reflect the President's FY 1983 Budget to Congress. Moneys allocated and estimated costs, and the construction status are tabulated for projects under the subject categories of: conservation and renewable energy; defense programs; environmental protection, safety and emergency preparedness; energy research; defense programs; nuclear energy; and management and administration

Technical support non-SLB(GCDF)

International Nuclear Information System (INIS)

DePoorter, G.L.; Burton, B.W.

1982-01-01

The Los Alamos National Laboratory is providing technical support for the Greater Confinement Demonstration Facility (GCDF) at the Nevada Test Site. This technical support consists of computer modeling of the GCDF, design and emplacement of a Shallow Test Plot at NTS, and instrument testing at Los Alamos. Results to date on the computer modeling and the Shallow Test Plot are described

Nondestructive analysis of the gold quarter liras

International Nuclear Information System (INIS)

Cakir, C.; Guerol, A.; Demir, L.; Sahin, Y.

2009-01-01

In this study, we have prepared seven Au-Cu standards in the concentration range of 18-24 (as carat) for nondestructive control of gold quarter liras. Some calibration curves for quantitative analysis of Au in the gold quarter liras that commercially present in Turkey have been plotted using these standard samples. The characteristic X-rays of Au and Cu emitted from these standard samples and the test sample with known composition are recorded by using a Ge(Li) detector. These calibration curves provide a nondestructive analysis of gold quarter liras with the uncertainties about 1.18%. (author)

Quarterly report of RCRA groundwater monitoring data for period October 1, 1992--December 31, 1992

International Nuclear Information System (INIS)

1993-04-01

Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs as defined in the Resource Conservation and Recovery Act of 1976 (RCRA); and Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilities, as amended (40 CFR 265). Compliance with the 40 CFR 265 regulations is required by the Washington Administrative Code (WAC) 173-303. Long-term laboratory contracts were approved on October 22, 1991. DataChem Laboratories of Salt Lake City, Utah, performs the hazardous chemicals analyses for the Hanford Site. Analyses for coliform bacteria are performed by Columbia/Biomedical Laboratories and for dioxin by TMS Analytical Services, Inc. International Technology Analytical Services Richland, Washington performs the radiochemical analyses. This quarterly report contains data that were received prior to March 8, 1993. This report may contain not only data from the October through December quarter but also data from earlier sampling events that were not previously reported

Status of Recent Developments in the Technical Standards of Japan

International Nuclear Information System (INIS)

Ahn, Hyung-Joon; Ahn, Sang-Kyu; Koh, Jae-Dong; Kim, Chang-Bum

2006-01-01

Japan has systematically revamped its technical standards for nuclear reactor facilities by formulating various performance regulations. Being part of a trend toward deregulation, such efforts toward social regulation is aimed at effectively operating administrative procedural laws to keep pace with global trends and enhance the benefits of deregulation under the principle of self-responsibility. Based on the collection of public opinions in February and March 2005, the Nuclear and Industrial Safety Agency(NISA) presented its position that it was required to promptly perform a flexible assessment of the technical feasibility of formulated society and association standards. Current, pressing issues are summarized as an early revision of technical standards regarding nuclear facilities for power generation, use of society and association standards, and the overhaul of nuclear safety regulations subject to performance regulations. Subjecting technical standards to performance regulations means stipulating the qualitative aspects of performance and the targets that certain facilities must achieve, which are not specific standards, but general compulsory standards. This study examines the early revision of technical standards on nuclear facilities for power generation and the status of the use of society and association standards, as well as introducing the details of revisions in the concrete containment vessel standards as specific examples

Seismic assessment of Technical Area V (TA-V).

Energy Technology Data Exchange (ETDEWEB)

Medrano, Carlos S.

2014-03-01

The Technical Area V (TA-V) Seismic Assessment Report was commissioned as part of Sandia National Laboratories (SNL) Self Assessment Requirement per DOE O 414.1, Quality Assurance, for seismic impact on existing facilities at Technical Area-V (TA-V). SNL TA-V facilities are located on an existing Uniform Building Code (UBC) Seismic Zone IIB Site within the physical boundary of the Kirtland Air Force Base (KAFB). The document delineates a summary of the existing facilities with their safety-significant structure, system and components, identifies DOE Guidance, conceptual framework, past assessments and the present Geological and Seismic conditions. Building upon the past information and the evolution of the new seismic design criteria, the document discusses the potential impact of the new standards and provides recommendations based upon the current International Building Code (IBC) per DOE O 420.1B, Facility Safety and DOE G 420.1-2, Guide for the Mitigation of Natural Phenomena Hazards for DOE Nuclear Facilities and Non-Nuclear Facilities.

Technical resource documents and technical handbooks for hazardous-wastes management

Energy Technology Data Exchange (ETDEWEB)

Schomaker, N.B.; Bliss, T.M.

1986-07-01

The Environmental Protection Agency is preparing a series of Technical Resource Documents (TRD's) and Technical Handbooks to provide best engineering control technology to meet the needs of the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA) respectively. These documents and handbooks are basically compilation of research efforts of the Land Pollution Control Division (LPCD) to date. The specific areas of research being conducted under the RCRA land disposal program relate to laboratory, pilot and field validation studies in cover systems, waste leaching and solidification, liner systems and disposal facility evaluation. The technical handbooks provide the EPA Program Offices and Regions, as well as the states and other interested parties, with the latest information relevant to remedial actions.

Quarterly report of RCRA groundwater monitoring data for period April 1, 1993 through June 30, 1993

Energy Technology Data Exchange (ETDEWEB)

Jungers, D.K.

1993-10-01

Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs. This report contains data from Hanford Site groundwater monitoring projects. Westinghouse Hanford Company (WHC) manages the RCRA groundwater monitoring projects for federal facilities on the Hanford Site. Project management, specifying data needs, performing quality control (QC) oversight, managing data, and preparing project sampling schedules are all parts of this responsibility. Pacific Northwest Laboratory (PNL) administers the contract for analytical services and provides groundwater sampling services to WHC for the RCRA groundwater monitoring program. This quarterly report contains data received between May 24 and August 20, 1993, which are the cutoff dates for this reporting period. This report may contain not only data from samples collected during the April through June quarter but also data from earlier sampling events that were not previously reported.

Quarterly coal statistics of OECD countries

Energy Technology Data Exchange (ETDEWEB)

1992-04-27

These quarterly statistics contain data from the fourth quarter 1990 to the fourth quarter 1991. The first set of tables (A1 to A30) show trends in production, trade, stock change and apparent consumption data for OECD countries. Tables B1 to B12 show detailed statistics for some major coal trade flows to and from OECD countries and average value in US dollars. A third set of tables, C1 to C12, show average import values and indices. The trade data have been extracted or derived from national and EEC customs statistics. An introductory section summarizes trends in coal supply and consumption, deliveries to thermal power stations; electricity production and final consumption of coal and tabulates EEC and Japanese steam coal and coking coal imports to major countries.

Nuclear facility decommissioning and site remedial actions

International Nuclear Information System (INIS)

Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

1989-09-01

The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords

Nuclear facility decommissioning and site remedial actions

Energy Technology Data Exchange (ETDEWEB)

Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

1989-09-01

The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

Communication in reducing facility siting risk

International Nuclear Information System (INIS)

Bisconti, A.S.

1992-01-01

Today, social considerations are as important as technical ones in siting new nuclear facilities. Siting any industrial facility has become extremely difficult in this era of not in my backyard (NIMBY). Even if NIMBY does not arise locally, well-organized national opposition groups can be counted on to step in to fan the flames, especially when the industrial facility has to do with anything nuclear. It is now generally recognized that the greatest risk of failure for new nuclear facilities is not technical but social. Applying lessons gained from past experience and social science research can help reduce that risk. From these lessons, six principles for public interaction and communication stand out: (1) create goodwill now; (2) involve the community early; (3) establish the need; (4) communicate controls, not risk; (5) avoid jargon; (6) understand your public

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.

Facilities evaluation report

International Nuclear Information System (INIS)

Sloan, P.A.; Edinborough, C.R.

1992-04-01

The Buried Waste Integrated Demonstration (BWID) is a program of the Department of Energy (DOE) Office of Technology Development whose mission is to evaluate different new and existing technologies and determine how well they address DOE community waste remediation problems. Twenty-three Technical Task Plans (TTPs) have been identified to support this mission during FY-92; 10 of these have identified some support requirements when demonstrations take place. Section 1 of this report describes the tasks supported by BWID, determines if a technical demonstration is proposed, and if so, identifies the support requirements requested by the TTP Principal Investigators. Section 2 of this report is an evaluation identifying facility characteristics of existing Idaho National Engineering Laboratory (INEL) facilities that may be considered for use in BWID technology demonstration activities

Energy efficiency in buildings. Yearbook 2013; Energieeffizienz in Gebaeuden. Jahrbuch 2013

Energy Technology Data Exchange (ETDEWEB)

Poeschk, Juergen (ed.)

2013-06-01

The book under consideration presents current political controversies and technical solutions. Numerous practical examples show in detail how the German building stock for energy transition can be made fit. 40 technical papers shed light on the following topics: policy strategies, efficiency concepts on the test stand, districts and quarters, positive results: The house as an energy source, energy storage facilities for buildings, and smart energy.

Conceptual design report for Central Waste Disposal Facility

International Nuclear Information System (INIS)

1984-01-01

The permanent facilities are defined, and cost estimates are provided for the disposal of Low-Level Radioactive Wastes (LLW) at the Central Waste Disposal Facility (CWDF). The waste designated for the Central Waste Disposal Facility will be generated by the Y-12 Plant, the Oak Ridge Gaseous Diffusion Plant, and the Oak Ridge National Laboratory. The facility will be operated by ORNL for the Office of Defense Waste and By-Products Management of the Deparment of Energy. The CWDF will be located on the Department of Energy's Oak Ridge Reservation, west of Highway 95 and south of Bear Creek Road. The body of this Conceptual Design Report (CDR) describes the permanent facilities required for the operation of the CWDF. Initial facilities, trenches, and minimal operating equipment will be provided in earlier projects. The disposal of LLW will be by shallow land burial in engineered trenches. DOE Order 5820 was used as the performance standard for the proper disposal of radioactive waste. The permanent facilities are intended for beneficial occupancy during the first quarter of fiscal year 1989. 3 references, 9 figures, 7 tables

Underground Facilities, Technological Challenges

CERN Document Server

Spooner, N

2010-01-01

This report gives a summary overview of the status of international under- ground facilities, in particular as relevant to long-baseline neutrino physics and neutrino astrophysics. The emphasis is on the technical feasibility aspects of creating the large underground infrastructures that will be needed in the fu- ture to house the necessary detectors of 100 kton to 1000 kton scale. There is great potential in Europe to build such a facility, both from the technical point of view and because Europe has a large concentration of the necessary engi- neering and geophysics expertise. The new LAGUNA collaboration has made rapid progress in determining the feasibility for a European site for such a large detector. It is becoming clear in fact that several locations are technically fea- sible in Europe. Combining this with the possibility of a new neutrino beam from CERN suggests a great opportunity for Europe to become the leading centre of neutrino studies, combining both neutrino astrophysics and neutrino beam stu...

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.

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-31

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

Writer`s guide for technical procedures

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-01

A primary objective of operations conducted in the US Department of Energy (DOE) complex is safety. Procedures are a critical element of maintaining a safety envelope to ensure safe facility operation. This DOE Writer`s Guide for Technical Procedures addresses the content, format, and style of technical procedures that prescribe production, operation of equipment and facilities, and maintenance activities. The DOE Writer`s Guide for Management Control Procedures and DOE Writer`s Guide for Emergency and Alarm Response Procedures are being developed to assist writers in developing nontechnical procedures. DOE is providing this guide to assist writers across the DOE complex in producing accurate, complete, and usable procedures that promote safe and efficient operations that comply with DOE orders, including DOE Order 5480.19, Conduct of Operations for DOE Facilities, and 5480.6, Safety of Department of Energy-Owned Nuclear Reactors.

12 CFR 630.40 - Contents of the quarterly report to investors.

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 6 2010-01-01 2010-01-01 false Contents of the quarterly report to investors... INVESTORS IN SYSTEMWIDE AND CONSOLIDATED BANK DEBT OBLIGATIONS OF THE FARM CREDIT SYSTEM Quarterly Reports to Investors § 630.40 Contents of the quarterly report to investors. (a) General. The quarterly...

Unlocking investment in cities: ELENA-EIB technical assistance facility

International Nuclear Information System (INIS)

Cicmanova, Jana; Garabetian, Thomas

2015-06-01

Energy Cities prepared a review of projects undertaken in the cities of Paris, Malmoe (in association with Lund and Helsingborg), Barcelona, Bristol and Brussels-Capital that received support from the ELENA-EIB facility. The aim of this study is to identify the ways in which technical assistance programs such as ELENA-EIB can help unlock investment in cities. The projects we reviewed (developed by Energy Cities' members) cover a wide array of sectors, from public building refurbishment to public transport or renewable energy production. These five projects illustrate how cities can focus on developing capacity in a long-term perspective, looking at the expected benefits of an investment or a support mechanism beyond that of the project itself. Overall, we found that project development assistance mechanisms such as ELENA can be beneficial to trigger investment for climate action in cities. Cities maximise the benefits of such a program by looking at how their climate-protection actions can generate benefits for the citizens, or how to systematically integrate climate action in other investment projects. Project development assistance (PDA) affects cities by allowing them to develop a new vision of the way they prepare an investment program. The search of synergies and the override of silo mentalities were a core element in the projects we reviewed. Indeed, the support provided by the European Union through ELENA-EIB is used by the local authorities to develop a transversal approach to climate action. The grant provided for PDA and the requirements of the ELENA-EIB facility represent an opportunity for local authorities to set up a new strategy regarding energy efficiency and renewable energy actions. It can be the necessary push for cities and local authorities to change the way they plan their investments, and develop projects to achieve their climate objectives. Besides, the grant is used for building long-term capacity in the development of investment programs

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

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

Technical specification upgrading at the Fast Flux Test Facility (FFTF)

International Nuclear Information System (INIS)

Baird, Q.L.; Franz, G.R.; Absher, K.R.

1985-01-01

The FFTF Technical Specifications were generated in 1977 and 1978 following submittal of the FSAR in 1976. A phased implementation program served to prepare the specifications for each stage of the plant startup with the complete specifications approved and implemented late in 1980 for the first ascent to full power. In January, 1983 WHC undertook an upgrading effort to implement changes to the FFTF technical specifications. This program has been pursued with appropriate attention to the CFR and industry standards and practice. Examples of these changes, discussion of the methods and planned activities for the future will be presented. Technical data will be provided to support the impact of specific limits. The benefits of changes and the criteria for change will be elaborated

Results for the First, Second, and Third Quarter Calendar Year 2015 Tank 50H WAC slurry samples chemical and radionuclide contaminants

Energy Technology Data Exchange (ETDEWEB)

Crawford, C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-02-18

This report details the chemical and radionuclide contaminant results for the characterization of the Calendar Year (CY) 2015 First, Second, and Third Quarter sampling of Tank 50H for the Saltstone Waste Acceptance Criteria (WAC) in effect at that time. Information from this characterization will be used by Defense Waste Processing Facility (DWPF) & Saltstone Facility Engineering (D&S-FE) to support the transfer of low-level aqueous waste from Tank 50H to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50H Waste Characterization System. Previous memoranda documenting the WAC analyses results have been issued for these three samples.

Quarterly report for the electricity market; Kvartalsrapport for kraftmarknaden

Energy Technology Data Exchange (ETDEWEB)

Eliston, Anton Jaynand; Waeringstad, Thomas; Holmqvist, Erik; Lund Per Tore Jensen; Magnussen, Ingrid; Willumsen, Mats Oivind; Vik, Martin Andreas; Rasmussen, Kristian; Pettersen, Finn Erik Ljaastad; Weir, David Edward; Thorsen, Kjell; Langseth, Benedicte; Skau, Seming Haakon

2013-02-01

In the fourth quarter of 2012 the total inflow was 20.4 TWh, 2.8 TWh less than normal and 11.3 TWh less than in the same quarter than in 2011. Meanwhile the weather was slightly colder than normal, which contributed to high production and normalization of reservoir fillings. At the end of the quarter, the reservoir level was 0.8 percentage points below normal for the season, while it was 4.5 percentage points over the beginning of the quarter. At the end of 2012 it was 9.9 percent landfill units lower than the same time in 2011. Norway had a power consumption of 37.2 TWh in the fourth quarter, an increase of 9 percent from last year. In 2012, consumption was 130.0 TWh, an increase of around 5 TWh from 2011. Power production in Norway was 39.2 TWh in the fourth quarter - an increase of 2.4 percent from last year. In 2012, production was 147.9 TWh, compared to 128.1 TWh in 2011. The production increase is due to high reservoir levels at the beginning of 2012, and more than normal inflow. This gave high exports abroad. In the quarter, Norway had a net export of 2 TWh of electricity and was 17.9 TWh in 2012. It is the highest since 2000. The good resource gave a relatively low price level in the wholesale market for electricity. The average spot price in the Norwegian market areas were NOK 268-277 / MWh in the fourth quarter. In 2012 the price was 217-236 NOK/ MWh.(eb)

Natural gas imports and exports: First quarter report 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

The Office of Fuels Programs prepares quarterly reports summarizing the data provided by companies authorized to import or export natural gas. Companies are required, as a condition of their authorizations, to file quarterly reports with the OFP. This quarter`s focus is market penetration of gas imports into New England. Attachments show the following: % takes to maximum firm contract levels and weighted average per unit price for the long-term importers, volumes and prices of gas purchased by long-term importers and exporters, volumes and prices for gas imported on short-term or spot market basis, and gas exported short-term to Canada and Mexico.

Environmental Hazards Assessment Program. Quarterly report, July 1994--September 1994

International Nuclear Information System (INIS)

1994-01-01

The objectives of the Environmental Hazards Assessment Program (EHAP) stated in the proposal to DOE are as follows: Development of a holistic, national basis for risk assessment, risk management, and risk communication that recognizes the direct impact of environmental hazards on the health and well-being of all; development of a pool of talented scientist and experts in cleanup activities, especially in human health aspects; identification of needs and development of programs addressing the critical shortage of well-educated, highly-skilled technical and scientific personnel to address the health oriented aspects of environmental restoration and waste management. This is a progress report of the first quarter of the third year of the grant. It reports progress against these grant objectives and the Program Implementation Plan (published at the end of the first year of the grant)

First quarter 2005 sales data

International Nuclear Information System (INIS)

2005-04-01

This press release brings information on the AREVA group sales data. First quarter 2005 sales for the group were 2,496 millions of euros, up 3,6% year-on-year from 2,41 millions. The change in foreign exchange rates between the two periods show a negative impact of 22 millions euros, which is much lower than in the first quarter of 2004. It analyzes also in more details the situation of the front end, the reactors and service division, the back end division, the transmission and distribution division and the connectors division. (A.L.B.)

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

International Nuclear Information System (INIS)

1992-01-01

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

Facility model for the Los Alamos Plutonium Facility

International Nuclear Information System (INIS)

Coulter, C.A.; Thomas, K.E.; Sohn, C.L.; Yarbro, T.F.; Hench, K.W.

1986-01-01

The Los Alamos Plutonium Facility contains more than sixty unit processes and handles a large variety of nuclear materials, including many forms of plutonium-bearing scrap. The management of the Plutonium Facility is supporting the development of a computer model of the facility as a means of effectively integrating the large amount of information required for material control, process planning, and facility development. The model is designed to provide a flexible, easily maintainable facility description that allows the faciltiy to be represented at any desired level of detail within a single modeling framework, and to do this using a model program and data files that can be read and understood by a technically qualified person without modeling experience. These characteristics were achieved by structuring the model so that all facility data is contained in data files, formulating the model in a simulation language that provides a flexible set of data structures and permits a near-English-language syntax, and using a description for unit processes that can represent either a true unit process or a major subsection of the facility. Use of the model is illustrated by applying it to two configurations of a fictitious nuclear material processing line

Spiraling Light with Magnetic Metamaterial Quarter-Wave Turbines.

Science.gov (United States)

Zeng, Jinwei; Luk, Ting S; Gao, Jie; Yang, Xiaodong

2017-09-19

Miniaturized quarter-wave plate devices empower spin to orbital angular momentum conversion and vector polarization formation, which serve as bridges connecting conventional optical beam and structured light. Enabling the manipulability of additional dimensions as the complex polarization and phase of light, quarter-wave plate devices are essential for exploring a plethora of applications based on orbital angular momentum or vector polarization, such as optical sensing, holography, and communication. Here we propose and demonstrate the magnetic metamaterial quarter-wave turbines at visible wavelength to produce radially and azimuthally polarized vector vortices from circularly polarized incident beam. The magnetic metamaterials function excellently as quarter-wave plates at single wavelength and maintain the quarter-wave phase retardation in broadband, while the turbine blades consist of multiple polar sections, each of which contains homogeneously oriented magnetic metamaterial gratings near azimuthal or radial directions to effectively convert circular polarization to linear polarization and induce phase shift under Pancharatnum-Berry's phase principle. The perspective concept of multiple polar sections of magnetic metamaterials can extend to other analogous designs in the strongly coupled nanostructures to accomplish many types of light phase-polarization manipulation and structured light conversion in the desired manner.

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

First Quarter Hanford Seismic Report for Fiscal Year 2010

Energy Technology Data Exchange (ETDEWEB)

Rohay, Alan C.; Sweeney, Mark D.; Hartshorn, Donald C.; Clayton, Ray E.; Devary, Joseph L.

2010-03-29

The Hanford Seismic Network and the Eastern Washington Regional Network consist of 44 individual sensor sites and 15 radio relay sites maintained by the Hanford Seismic Assessment Team. The Hanford Seismic Network recorded 81 local earthquakes during the first quarter of FY 2010. Sixty-five of these earthquakes were detected in the vicinity of Wooded Island, located about eight miles north of Richland just west of the Columbia River. The Wooded Island events recorded this quarter is a continuation of the swarm events observed during fiscal year 2009 and reported in previous quarterly and annual reports (Rohay et al; 2009a, 2009b, 2009c, and 2009d). Most of the events were considered minor (coda-length magnitude [Mc] less than 1.0) with only 1 event in the 2.0-3.0 range; the maximum magnitude event (2.5 Mc) occurred on December 22 at depth 2.1 km. The average depth of the Wooded Island events during the quarter was 1.4 km with a maximum depth estimated at 3.1 km. This placed the Wooded Island events within the Columbia River Basalt Group (CRBG). The low magnitude of the Wooded Island events has made them undetectable to all but local area residents. The Hanford SMA network was triggered several times by these events and the SMA recordings are discussed in section 6.0. During the last year some Hanford employees working within a few miles of the swarm area and individuals living directly across the Columbia River from the swarm center have reported feeling many of the larger magnitude events. Strong motion accelerometer (SMA) units installed directly above the swarm area at ground surface measured peak ground accelerations approaching 15% g, the largest values recorded at Hanford. This corresponds to strong shaking of the ground, consistent with what people in the local area have reported. However, the duration and magnitude of these swarm events should not result in any structural damage to facilities. The USGS performed a geophysical survey using satellite

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

Wind/photovoltaic power indicators. Third quarter 2010

International Nuclear Information System (INIS)

2010-01-01

This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

Wind/photovoltaic power indicators. Second quarter 2009

International Nuclear Information System (INIS)

2009-09-01

This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

Wind/photovoltaic power indicators. Second quarter 2011

International Nuclear Information System (INIS)

2011-01-01

This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

Wind/photovoltaic power indicators. First quarter 2010

International Nuclear Information System (INIS)

2010-01-01

This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

Wind/photovoltaic power indicators. Second quarter 2010

International Nuclear Information System (INIS)

2010-01-01

This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

Wind/photovoltaic power indicators. Fourth quarter 2010

International Nuclear Information System (INIS)

2011-01-01

This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

Wind/photovoltaic power indicators. First quarter 2011

International Nuclear Information System (INIS)

2011-01-01

This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

Wind/photovoltaic power indicators. Third quarter 2009

International Nuclear Information System (INIS)

2009-11-01

This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

Wind/photovoltaic power indicators. Fourth quarter 2009

International Nuclear Information System (INIS)

2010-02-01

This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

Technical justification for a request to reclassify the former CCC/USDA facility at Canada, Kansas.

Energy Technology Data Exchange (ETDEWEB)

LaFreniere, L. M.; Environmental Science Division

2007-12-21

Contamination in groundwater at Canada, Kansas, was discovered in 1997, during limited private well sampling near former grain storage facilities of the Commodity Credit Corporation, U.S. Department of Agriculture (CCC/USDA). Subsequent investigations by the Kansas Department of Health and Environment (KDHE) confirmed carbon tetrachloride and nitrate concentrations in groundwater above the respective maximum contaminant levels (MCLs) of 5.0 {micro}g/L and 10.0 mg/L. The KDHE investigations identified both the former CCC/USDA grain storage facility and a private grain storage facility as likely sources for the carbon tetrachloride contamination. The CCC/USDA funded extension of a rural water district line to provide a permanent alternate water supply, and the KDHE has conducted long-term monitoring under the State Water Plan. This document presents an analysis of the available information for the Canada site, acquired in previous investigations and the long-term KDHE monitoring. This analysis forms the technical justification for a request to reclassify the former CCC/USDA grain storage facility at Canada as a site requiring no further action under the Intergovernmental Agreement (IGA) between the KDHE and the USDA's Farm Service Agency. The KDHE's long-term water level monitoring results indicate a consistent groundwater flow direction to the east-southeast. Consequently, the wells with the highest overall concentrations of carbon tetrachloride are downgradient from the private grain storage facility but not downgradient from the former CCC/USDA facility. The KDHE criterion for reclassification of a site is that contamination there should not pose an unacceptable risk, on the basis of analytical results for four consecutive, equally timed, sequenced sampling episodes over a period of no less than two years. In seven KDHE sampling events over a period of six years (2001-2007), the concentrations of carbon tetrachloride in the monitoring well on the former

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.