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

Energy Technology Data Exchange (ETDEWEB)

Tossavainen, K. [ed.

1995-03-01

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

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

International Nuclear Information System (INIS)

Tossavainen, K.

1995-03-01

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

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

Energy Technology Data Exchange (ETDEWEB)

1994-08-18

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

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

International Nuclear Information System (INIS)

Stevenson, L.L.

1998-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-09-01

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

Solar pilot plant, phase I. Quarterly report No. 1, July--December 1975

Energy Technology Data Exchange (ETDEWEB)

None

1976-02-20

Honeywell Inc. is investigating the technical and economic feasibility of generating electricity from solar energy. During the first 6 months of the program (1 July--31 December 1975), a preliminary design baseline for a 10-MW(e) solar pilot plant was generated and analyzed. Subsequently, several changes were made to improve performance and/or reduce cost. Conceptual designs and research experiments were generated for three key subsystems--collector, steam generator, and thermal storage. Limited testing was done to study the problem of removing eutectic salts from vaporizer tubes in the thermal storage subsystem. The program was on schedule at the end of 1975. Plans for the first quarter of 1976 include ordering long-leadtime items for the subsystem research experiments, continuing analysis of the conceptual designs preparatory to detailing them, and continuing engineering model experiments.

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

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

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

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

International Nuclear Information System (INIS)

1994-01-01

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

Coal demonstration plants. Quarterly report, April-June 1979

Energy Technology Data Exchange (ETDEWEB)

None

1980-04-01

The objective of the US DOE demonstration program is to demonstrate and verify second-generation technologies and validate the economic, environmental and productive capacity of a near commercial-size plant by integrating and operating a modular unit using commercial size equipment. These facilities are the final stage in the RD and D process aimed at accelerating and reducing the risks of industrial process implementation. Under the DOE program, contracts for the design, construction, and operation of the demonstration plants are awarded through competitive procedures and are cost shared with the industrial partner. The conceptual design phase is funded by the government, with the detailed design, procurement, construction, and operation phases being co-funded between industry and the government. The government share of the cost involved for a demonstration plant depends on the plant size, location, and the desirability and risk of the process to be demonstrated. The various plants and programs are discussed: Description and status, funding, history, flowsheet and progress during the current quarter. (LTN)

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

International Nuclear Information System (INIS)

1982-11-01

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

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

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

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

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

Studies of potential severe accidents in Finnish nuclear power plants. Quarterly report 3. quarter 1987

International Nuclear Information System (INIS)

Aro, Ilari.

1989-07-01

This thesis is based on six publications dealing with severe accident studies in Finnish nuclear power plants. Main emphasis has been put on general technical bases and methodologies applied in severe accident evaluation in Finland. As an example of the use of the analysis and evaluation methods, the analysis of one representative accident sequence, t otal loss of AC power , has been presented for both Finnish power plant types. This accident sequence is required to be analyzed in the Finnish safety guide YVL 2.2 which deals with transient and accident analyses as a basis of technical solutions at nuclear powr plants. Two different analysis methods, MAAP 3.0 and MARCH 3/STCP have been used for receiving as complete a picture as possible of the flow of events and for verifying the models to some extent. Besides the use of the two different models, the method of sensitivity analysis has been used for evaluating the effects of some important technical parameters on the accident flow. Finally, conclusions of the applicability of the two methods for analyzing severe accident sequences in Finnish plants have been discussed

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.

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.

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

VGB-requirements regarding technical data for power plants

International Nuclear Information System (INIS)

Richnow, Joerg

2009-01-01

Much of the technical plant data resulting from the planning, construction and start-up of power plants is needed for subsequent management and maintenance. Because of this, VGB has taken the initiative and has defined standard minimum requirements from power plant operators for technical plant data. They relate to the details and structure of this data, the definition of material classes and characteristics for the main power plant components and IT implementation for delivery of the technical plant data. (orig.)

Standard Technical Specifications, Westinghouse plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document, Volume 3, contains the Bases for Sections 3.4--3.9 of the improved STS

Standard Technical Specifications, Westinghouse Plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the unproved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS which contain information on safety limits, reactivity control systems, power distribution limits, and instrumentation

Standard Technical Specifications, Westinghouse plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

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.

Standard technical specifications combustion engineering plants

International Nuclear Information System (INIS)

1992-09-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS) for Combustion Engineering Plants. The improved STS wee developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Sections 3.4--3.9 of the improved STS

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.

Standard Technical Specifications, Babcock and Wilcox Plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) plants and documents the positions of the Nuclear Regulatory Commission (NRC) based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council. The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for developing improved plant-specific technical specifications by individual nuclear power plant licensees. This volume contains sections 3.4--3.9 which cover: Reactor coolant systems, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations

Standard Technical Specifications, Combustion Engineering plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (M) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

Standard Technical Specifications, Combustion Engineering plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved SM. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3 contains the Bases for Sections 3.4--3.9 of the improved M

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.

Standard Technical Specifications, Babcock and Wilcox plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The unproved STS were developed based on the, criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop proved plant-specific technical specifications. This report contains three volumes. This document, Volume 1 contains the Specifications for all chapters and sections of the improved STS

(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.

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.

Nuclear Power Plant Temelin Technical Support Centre

International Nuclear Information System (INIS)

Krizek, K.

2000-01-01

The erection of the Technical Support Centre for the Nuclear Power Plant Temelin has been a relatively sophisticated and costly issue. It was by proper use of the existing systems, as e.g. I and C, ISE and other systems, that a robust system has been created that is able to meet any requirements laid on the performance of the Technical Support Centre. The decision of the utility CEZ, a.s. that made it possible to establish the Technical Support Centre at the Nuclear Power Plant Temelin has been a right step which shows the level of safety culture within the utility. (author)

Standard Technical Specifications, Babcock and Wilcox plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

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.

Hanford Waste Vitrification Plant technical manual

Energy Technology Data Exchange (ETDEWEB)

Larson, D.E. [ed.; Watrous, R.A.; Kruger, O.L. [and others

1996-03-01

A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version.

Hanford Waste Vitrification Plant technical manual

International Nuclear Information System (INIS)

Larson, D.E.; Watrous, R.A.; Kruger, O.L.

1996-03-01

A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version

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

Tele-maintenance 'intelligent' system for technical plants result management

International Nuclear Information System (INIS)

Concetti, Massimo; Cuccioletta, Roberto; Fedele, Lorenzo; Mercuri, Giampiero

2009-01-01

The management of technical plant for productivity and safety is generally a complex activity, particularly when many plants distributed in the territory are considered (i.e. the more and more frequent case of outsourced plants maintenance by specialized companies), granted quality and cost results are required (i.e. the case of some rather innovative contract solutions) and the technology involved is heterogeneous and innovative (i.e. electro-mechanical plants). In order to efficiently achieve the above aims an 'intelligent' maintenance-management system for the distant monitoring and controlling by a remote control center has been developed. The so-called GrAMS (granted availability management system) system is conceived to give to organizations involved in technical-industrial plants management the possibility to tend to a 'well-known availability' and 'zero-failures' management. In particular, this study deals with the diagnostic aspects and safety level of technical plants (such as elevators, thermo-technical plants, etc.), and with the involvement of ad hoc designed software analysis tools based on neural networks and reliability indicators. Part of the research dealing with the tele-maintenance intelligent system has been financed by the Italian High Institute for Safety (ISPESL) and led to the development of a pre-industrial prototype whose realization and testing is here described

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

Standard Technical Specifications, General Electric Plants, BWR/6

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

Standard Technical Specifications, General Electric plants, BWR/4

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

Standard Technical Specifications, General Electric plants, BWR/6

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

Standard Technical Specifications, General Electric Plants, BWR/6

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

Standard Technical Specifications, General Electric plants, BWR/4

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

Solar pilot plant, phase I. Quarterly report No. 2, January--March 1976

Energy Technology Data Exchange (ETDEWEB)

None

1976-08-20

During the report period, conceptual designs for the collector and steam generator subsystem research experiments (SREs) were approved, and design detailing began. The thermal storage SRE concept was modified through additional analyses and engineering model experiments and resubmitted for evaluation. Detailed designs for all three subsystems will be submitted during the next quarter. Preparation for SRE testing proceeded through procurement of long-leadtime items and detailed definition of test arrangements. Analysis and design of the electrical generation subsystem and balance of the plant proceeded essentially on schedule.

Standard technical specifications: Babcock and Wilcox Plants. Revision 1

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Babcock ampersand Wilcox Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

An analysis of factors that influence the technical efficiency of Malaysian thermal power plants

International Nuclear Information System (INIS)

See, Kok Fong; Coelli, Tim

2012-01-01

The main objectives of this paper are to measure the technical efficiency levels of Malaysian thermal power plants and to investigate the degree to which various factors influence efficiency levels in these plants. Stochastic frontier analysis (SFA) methods are applied to plant-level data over an eight year period from 1998 to 2005. This is the first comprehensive analysis (to our knowledge) of technical efficiency in the Malaysian electricity generation industry using parametric method. Our empirical results indicate that ownership, plant size and fuel type have a significant influence on technical efficiency levels. We find that publicly-owned power plants obtain average technical efficiencies of 0.68, which is lower than privately-owned power plants, which achieve average technical efficiencies of 0.88. We also observe that larger power plants with more capacity and gas-fired power plants tend to be more technically efficient than other power plants. Finally, we find that plant age and peaking plant type have no statistically significant influence on the technical efficiencies of Malaysian thermal power plants. - Highlights: ► We examine the technical efficiency (TE) levels of Malaysian thermal power plants. ► We also investigate the degree to which various factors influence efficiency levels in these plants. ► Stochastic frontier analysis methods are used. ► Average plant would have to increase their TE level by 21% to reach the efficient frontier. ► Ownership, plant size and fuel type have a significant influence on the TE levels.

Technical evaluation of bids for nuclear power plants

International Nuclear Information System (INIS)

1981-01-01

In continuation of its efforts to provide comprehensive and impartial guidance to Member States facing the need to introduce nuclear power, the International Atomic Energy Agency is issuing this guidebook as part of a series of guidebooks and codes of practice and, in particular, as a necessary supplement to 'Economic Evaluation of Bids for Nuclear Power Plants: A Guidebook', published by the IAEA in 1976 as Technical Reports Series No.175. The present publication is intended for project managers and senior engineers of electric utilities who are concerned with the evaluation of bids for a nuclear power project. It assumes that the reader has a good knowledge of the technical characteristics of nuclear power plants and of nuclear power project implementation. Its purpose is to provide the information necessary to organize, guide and supervise the technical evaluation of bids for a nuclear power project. It goes without saying that the technical staff carrying out the evaluation must have prior technical experience which cannot be provided by a guidebook

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

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

Energy Technology Data Exchange (ETDEWEB)

1993-12-31

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

Technical strategy map to employing nuclear power plant aging management

International Nuclear Information System (INIS)

Sekimura, Naoto; Kanno, Masanori

2008-01-01

Stated in this report are back ground of technical strategy map for nuclear power plant aging management, result of the first road map, significance of technical strategy map, introduction scenario, technology map, road map, upgrade in every year, three groups of academia, industry and government, plan of technical strategy map, upgrade system, comprehensive introduction scenario, measures of nuclear power plant aging management in Japan and the world, new inspection system, outline of 'technical strategy map 2008', preparation of technical information bases in industry, academia and government, collaboration of them, safety researches of neutron radiation damage, stress corrosion crack, fatigue, piping thinning, insulation degradation, concrete degradation, thermal aging, evaluation technologies of earthquake resistance, preparation of rules and standards, ideal maintenance, and training talent. (S.Y.)

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.)

Have U.S. power plants become less technically efficient? The impact of carbon emission regulation

International Nuclear Information System (INIS)

Zhou, Yishu; Huang, Ling

2016-01-01

We estimate directional distance functions to measure the impact of carbon emission regulation, the Regional Greenhouse Gas Initiative (RGGI) in particular, on U.S. power plants' technical efficiency. The model shows that the average technical efficiency scores for coal and natural gas plants are 88.70% and 83.14% respectively, indicating a very technically efficient industry. We find no evidence of technical efficiency changes due to the RGGI regime in the RGGI area. In the same area, relatively less efficient coal plants exited the market and slightly more efficient natural gas plants entered, compared to the incumbent plants. In addition, some evidence of a spillover effect is found. Using a counterfactual analysis, the RGGI regulation leads to a 1.48% decline in the average technical efficiency for coal plants within neighboring states of RGGI during 2009–2013. - Highlights: • RGGI does not lead to a change in the technical efficiency of RGGI power plants. • Less efficient coal plants exit. • Entering natural gas plants are more efficient. • RGGI has a spillover effect on neighboring coal plants.

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

Technical diagnostics - equipment monitoring for increasing safety and availability of nuclear power plants

International Nuclear Information System (INIS)

Sturm, A.; Foerster, R.

1977-01-01

Utilization of technical diagnostics in equipment monitoring of nuclear power plants for ensuring nuclear safety, economic availability, and for decision making on necessary maintenance is reviewed. Technical diagnostics is subdivided into inspection and early detection of malfunctions. Moreover, combination of technical diagnostics and equipment monitoring, integration of technical diagnostics into maintenance strategy, and problems of introducing early detection of malfunctions into maintenance management of nuclear power plants are also discussed. In addition, a compilation of measuring techniques used in technical diagnostics has been made. The international state of the art of equipment monitoring in PWR nuclear power plants is illustrated by description of the sound and vibration measuring techniques. (author)

Radiological Effluent Technical Specifications (RETS) implementation, Kewaunee Nuclear Power Plant

International Nuclear Information System (INIS)

Serrano, W.; Akers, D.W.

1985-06-01

A review of the Radiological Effluent Technical Specifications (RETS) for the Kewaunee Nuclear Power Plant was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7'' of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual and the Radiological Environmental Monitoring Manual were reviewed and generally found to be in compliance with the NRC review guidelines

Wind/photovoltaic power indicators. First quarter 2012

International Nuclear Information System (INIS)

Thienard, Helene

2012-06-01

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, projects in progress, regional status. (J.S.)

Wind/photovoltaic power indicators. Second quarter 2015

International Nuclear Information System (INIS)

Reynaud, Didier

2015-08-01

This document presents a quarterly review of power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional balance sheet

Wind/photovoltaic power indicators. Third quarter 2011

International Nuclear Information System (INIS)

Thienard, Helene

2011-11-01

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, projects in progress, regional status. (J.S.)

Wind/photovoltaic power indicators. Third quarter 2014

International Nuclear Information System (INIS)

Reynaud, Didier

2014-11-01

This document presents a quarterly review of power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional balance sheet

Wind/photovoltaic power indicators. Fourth quarter 2012

International Nuclear Information System (INIS)

Reynaud, Didier; Thienard, Helene

2013-02-01

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 distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional status. (J.S.)

Wind/photovoltaic power indicators. Third quarter 2010

International Nuclear Information System (INIS)

Thienard, Helene

2010-11-01

This document presents a quarterly review of power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional balance sheet

Wind/photovoltaic power indicators. Fourth quarter 2013

International Nuclear Information System (INIS)

Reynaud, Didier

2014-02-01

This document presents a quarterly review 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 distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional status

Wind/photovoltaic power indicators. Third quarter 2013

International Nuclear Information System (INIS)

Reynaud, Didier

2013-11-01

This document presents a quarterly review 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 distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional status

Wind/photovoltaic power indicators. Fourth quarter 2011

International Nuclear Information System (INIS)

Thienard, Helene

2012-02-01

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, projects in progress, regional status. (J.S.)

Wind/photovoltaic power indicators. Third quarter 2012

International Nuclear Information System (INIS)

Thienard, Helene

2012-11-01

This document presents a quarterly review of power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional balance sheet

Wind/photovoltaic power indicators. First quarter 2014

International Nuclear Information System (INIS)

Reynaud, Didier

2014-05-01

This document presents a quarterly review 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 distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional status

Wind/photovoltaic power indicators. Second quarter 2012

International Nuclear Information System (INIS)

Thienard, Helene

2012-09-01

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, projects in progress, regional status. (J.S.)

Wind/photovoltaic power indicators. First quarter 2013

International Nuclear Information System (INIS)

Reynaud, Didier; Thienard, Helene

2013-06-01

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 distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional status. (J.S.)

Wind/photovoltaic power indicators. Forth quarter 2014

International Nuclear Information System (INIS)

Reynaud, Didier

2015-02-01

This document presents a quarterly review of power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional balance sheet

Wind/photovoltaic power indicators. Second quarter 2014

International Nuclear Information System (INIS)

Reynaud, Didier

2014-08-01

This document presents a quarterly review 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 distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional balance sheet

Standard technical specifications: Combustion engineering plants. Volume 1, Revision 1: Specifications

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Combustion Engineering Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

NST Quarterly. July 1996 issue

International Nuclear Information System (INIS)

1996-01-01

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

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.

The impact of technical specification surveillance requirements and allowable outage times on plant availability

International Nuclear Information System (INIS)

Webster, S.A.; Finnicum, D.J.

1985-01-01

Surveillances required to be conducted by a plant's Technical Specifications have resulted in plant shutdowns and lost availability. This paper looks at shutdowns which have occurred due to required surveillance testing and insufficient repair time allowed by Technical Specifications. A loss of plant availability of almost 3% per plant year was found for U.S. pressurized water reactors during the five year period, 1979 to 1984. This figure excludes major problems which required plant shutdown whether or not mandated by the Technical Specifications. In addition to their affect on availability, such shutdowns can add to the challenges to plant safety systems and can affect plant aging by increasing the thermal cycles on plant components

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

Environmental efficiency among corn ethanol plants

International Nuclear Information System (INIS)

Sesmero, Juan P.; Perrin, Richard K.; Fulginiti, Lilyan E.

2012-01-01

Economic viability of the US corn ethanol industry depends on prices, technical and economic efficiency of plants and the extent of policy support. Public policy support is tied to the environmental efficiency of plants measured as their impact on emissions of greenhouse gases. This study evaluates the environmental efficiency of seven recently constructed ethanol plants in the North Central region of the US, using nonparametric data envelopment analysis (DEA). The minimum feasible level of GHG emissions per unit of ethanol is calculated for each plant and this level is decomposed into its technical and allocative sources. Results show that, on average, plants in our sample may be able to reduce GHG emissions by a maximum of 6% or by 2.94 Gg per quarter. Input and output allocations that maximize returns over operating costs (ROOC) are also found based on observed prices. The environmentally efficient allocation, the ROOC-maximizing allocation, and the observed allocation for each plant are combined to calculate economic (shadow) cost of reducing greenhouse gas emissions. These shadow costs gauge the extent to which there is a trade off or a complementarity between environmental and economic targets. Results reveal that, at current activity levels, plants may have room for simultaneous improvement of environmental efficiency and economic profitability. -- Highlights: ► Environmental efficiency of ethanol plants in the North Central US is evaluated. ► Economic (shadow) cost of reducing greenhouse gas emissions is calculated. ► Feasible changes in the mix of inputs and byproducts can reduce GHG emissions. ► On average plants may be able to reduce GHG emissions by 2.94 Gg per quarter. ► GHG reductions may be achieved at a moderate or zero operating cost.

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

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

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

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.

Trend chart: photovoltaic solar energy. Forth quarter 2016

International Nuclear Information System (INIS)

Coltier, Yves

2017-02-01

This publication presents a quarterly review of power generation from photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, detailed regional results, methodology used

Trend chart: photovoltaic solar energy. Third quarter 2016

International Nuclear Information System (INIS)

Coltier, Yves

2016-11-01

This publication presents a quarterly review of power generation from photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, detailed regional results, methodology used

Trend chart: photovoltaic solar energy. Forth quarter 2015

International Nuclear Information System (INIS)

Reynaud, Didier

2016-02-01

This publication presents a quarterly review of power generation from photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, detailed regional results, methodology used

Trend chart: photovoltaic solar energy. First quarter 2017

International Nuclear Information System (INIS)

2017-05-01

This publication presents a quarterly review of power generation from photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, detailed regional results, methodology used

NST Quarterly - Oct 2000 issue

International Nuclear Information System (INIS)

2000-01-01

NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights the bioremediation of soils, the use of biological agents to reclaim soils and water polluted by substances hazardous to human health and/or the environment. Integrated waste management and thermal oxidation plant also reported, the topics discussed includes the role of the integrated waste management system, plant description and equipment design

Standard technical specifications General Electric plants, BWR/6. Volume 1, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/6 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

Preparation of radiological effluent technical specifications for nuclear power plants. a guidance manual for users of standard technical specifications

International Nuclear Information System (INIS)

Boegli, J.S.; Bellamy, R.R.; Britz, W.L.; Waterfield, R.L.

1978-10-01

The purpose of this manual is to describe methods found acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for the calculation of certain key values required in the preparation of proposed radiological effluent Technical Specifications using the Standard Technical Specifications for light-water-cooled nuclear power plants. This manual also provides guidance to applicants for operating licenses for nuclear power plants in the preparation of proposed radiological effluent Technical Specifications or in preparing requests for changes to existing radiological effluent Technical Specifications for operating licenses. The manual additionally describes current staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems

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.

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.

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.

A Study on Establishment of Nuclear Power Plant Technical Support System and Activation Plan

International Nuclear Information System (INIS)

Wi, M. H.; Park, W. S.; Lee, H. S.; Kim, J. H.; Won, B. C.; Kim, Y. H.; Goo, D. S.; Choi, H. B.

2009-11-01

This report includes activities related to establishment of 'BaroBaro nuclear plant technical support center', 'selection of nuclear plant applicable technology', and 'various information interchange between KAERI and nuclear power plant'. 'BaraBaro center was newly organized to support on resolving the technical difficulties in operation of nuclear power plant'. The center consists of 10 technical parts and a leading expert is assigned to each part to support more efficiently. This center is always served for 24 hour. The plant operators can register their problem to the center by a call, e-mail, or internet and they can receive the answer about what they issued from KAERI experts. To make a brochure, we selected 32 technologies which are applicable in nuclear plant without additional R and D activity. The brochure was distributed to the officer in charge of nuclear plant operations. Various meetings were held to increase interchange of experience and technology between KAERI and nuclear power plant and we discussed many different issues at that meeting

Fuel management study on quarter core refueling for Ling Ao NPP

International Nuclear Information System (INIS)

Zhang Hong; Li Jinggang

2012-01-01

The fuel management study on quarter core refueling is introduced for Ling Ao NPP. Starting from the selection of the objective of fuel management for quarter core refueling, the code and method used and the analysis carried out are explained in details to reach the final loading pattern chosen. The start-up physics test results are listed to demonstrate the realized quarter core fuel management. In the end, the advantage and disadvantage after turning to quarter core refueling has been given for the power plant from the fuel management point of view. (authors)

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.

Technical evaluation of RETS-required reports for Kewaunee Nuclear Power Plant for 1983

International Nuclear Information System (INIS)

Magleby, E.H.; Young, T.E.

1985-01-01

A review of the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at the Kewaunee Nuclear Power Plant during 1983 was performed. The periodic reports reviewed were the two Semiannual Effluent Release Reports for 1983 and the annual Kewaunee Environmental Radioactivity Survey. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

(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.

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

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.

Standard technical specifications: General Electric plants, BWR/4. Volume 1, Revision 1: Specifications

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

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

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.

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.

Standard Technical Specifications, General Electric plants, BWR/4

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power specifications. This report contains three volumes. This document, Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS

Risk-based analysis methods applied to nuclear power plant technical specifications

International Nuclear Information System (INIS)

Wagner, D.P.; Minton, L.A.; Gaertner, J.P.

1989-01-01

A computer-aided methodology and practical applications of risk-based evaluation of technical specifications are described. The methodology, developed for use by the utility industry, is a part of the overall process of improving nuclear power plant technical specifications. The SOCRATES computer program uses the results of a probabilistic risk assessment or a system-level risk analysis to calculate changes in risk due to changes in the surveillance test interval and/or the allowed outage time stated in the technical specification. The computer program can accommodate various testing strategies (such as staggered or simultaneous testing) to allow modeling of component testing as it is carried out at the plant. The methods and computer program are an integral part of a larger decision process aimed at determining benefits from technical specification changes. These benefits can include cost savings to the utilities by reducing forced shutdowns and decreasing labor requirements for test and maintenance activities, with no adverse impacts on risk. The methodology and the SOCRATES computer program have been used extensively toe valuate several actual technical specifications in case studies demonstrating the methods. Summaries of these applications demonstrate the types of results achieved and the usefulness of the risk-based evaluation in improving the technical specifications

U Plant Aggregate Area Management study technical baseline report

International Nuclear Information System (INIS)

DeFord, D.H.; Carpenter, R.W.

1995-05-01

This document was prepared in support of an Aggregate Area Management Study of U Plant. It provides a technical baseline of the aggregate area and results from an environmental investigation that was undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC), which is currently the Waste Site and Facility Research Office, Natural Resources, Bechtel Hanford, Inc. (BHI). It is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. U Plant refers to the 221-U Process Canyon Building, a chemical separation facility constructed during World War II. It also includes the Uranium Oxide (UO 3 ) Plant constructed at the same time as 221-U as an adjunct to the original plutonium separation process but which, like 221-U, was converted for other missions. Waste sites are associated primarily with U Plant's 1952 through 1958 Uranium Metal Recovery Program mission and the U0 3 Plant's ongoing U0 3 mission. Waste sites include cribs, reverse wells, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, a waste vault, and the lines and encasements that connect them. It also includes the U Pond and its feed ditches and an underground tank farm designed for high-level liquid wastes

Guidelines for the technical evaluation of replacement items in nuclear power plants (NCIG-11)

International Nuclear Information System (INIS)

Craig, W.E.; Fakhar, A.A.; Shulman, M.N.

1989-12-01

This document presents guidelines and supporting information for the technical evaluation of replacement items in nuclear power plants. These guidelines contain six major sections which provide the practical knowledge and a programmatic approach to determine the technical and quality requirements necessary to generate purchase documents to procure the proper replacement items. The technical evaluation methodology includes the following steps. (1) Identification of the need for a technical evaluation. (2) Component/part functional classification procedures. (3) Performance of a Failure Modes and Effects Analysis. (4) Selection of Critical Characteristics for Design Determination. (5) Performance of a ''Like-For-Like'' or ''Alternate'' item Evaluation. (6) Preparation of the Technical and Quality Requirements Specification. Work on this document was initiated in response to the increased emphasis by the utilities owning nuclear power plants and nuclear industry on procurement of replacement items for use in safety related applications at nuclear power plants. 20 refs., 9 figs., 14 tabs

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

International Nuclear Information System (INIS)

1993-01-01

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

Variations of Histone Modification Patterns: Contributions of Inter-plant Variability and Technical Factors

Directory of Open Access Journals (Sweden)

Sylva Brabencová

2017-12-01

Full Text Available Inter-individual variability of conspecific plants is governed by differences in their genetically determined growth and development traits, environmental conditions, and adaptive responses under epigenetic control involving histone post-translational modifications. The apparent variability in histone modifications among plants might be increased by technical variation introduced in sample processing during epigenetic analyses. Thus, to detect true variations in epigenetic histone patterns associated with given factors, the basal variability among samples that is not associated with them must be estimated. To improve knowledge of relative contribution of biological and technical variation, mass spectrometry was used to examine histone modification patterns (acetylation and methylation among Arabidopsis thaliana plants of ecotypes Columbia 0 (Col-0 and Wassilewskija (Ws homogenized by two techniques (grinding in a cryomill or with a mortar and pestle. We found little difference in histone modification profiles between the ecotypes. However, in comparison of the biological and technical components of variability, we found consistently higher inter-individual variability in histone mark levels among Ws plants than among Col-0 plants (grown from seeds collected either from single plants or sets of plants. Thus, more replicates of Ws would be needed for rigorous analysis of epigenetic marks. Regarding technical variability, the cryomill introduced detectably more heterogeneity in the data than the mortar and pestle treatment, but mass spectrometric analyses had minor apparent effects. Our study shows that it is essential to consider inter-sample variance and estimate suitable numbers of biological replicates for statistical analysis for each studied organism when investigating changes in epigenetic histone profiles.

Variations of Histone Modification Patterns: Contributions of Inter-plant Variability and Technical Factors.

Science.gov (United States)

Brabencová, Sylva; Ihnatová, Ivana; Potěšil, David; Fojtová, Miloslava; Fajkus, Jiří; Zdráhal, Zbyněk; Lochmanová, Gabriela

2017-01-01

Inter-individual variability of conspecific plants is governed by differences in their genetically determined growth and development traits, environmental conditions, and adaptive responses under epigenetic control involving histone post-translational modifications. The apparent variability in histone modifications among plants might be increased by technical variation introduced in sample processing during epigenetic analyses. Thus, to detect true variations in epigenetic histone patterns associated with given factors, the basal variability among samples that is not associated with them must be estimated. To improve knowledge of relative contribution of biological and technical variation, mass spectrometry was used to examine histone modification patterns (acetylation and methylation) among Arabidopsis thaliana plants of ecotypes Columbia 0 (Col-0) and Wassilewskija (Ws) homogenized by two techniques (grinding in a cryomill or with a mortar and pestle). We found little difference in histone modification profiles between the ecotypes. However, in comparison of the biological and technical components of variability, we found consistently higher inter-individual variability in histone mark levels among Ws plants than among Col-0 plants (grown from seeds collected either from single plants or sets of plants). Thus, more replicates of Ws would be needed for rigorous analysis of epigenetic marks. Regarding technical variability, the cryomill introduced detectably more heterogeneity in the data than the mortar and pestle treatment, but mass spectrometric analyses had minor apparent effects. Our study shows that it is essential to consider inter-sample variance and estimate suitable numbers of biological replicates for statistical analysis for each studied organism when investigating changes in epigenetic histone profiles.

Improved technical specifications and related improvements to safety in commercial Nuclear power plants

International Nuclear Information System (INIS)

Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C.

2004-01-01

Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

Improved technical specifications and related improvements to safety in commercial Nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C. [EXCEL Services Corporation, 11921 Rockville Pike, Suite 100, Rockville, MD 20852 (United States)]. e-mail: donaldh@excelservices.com

2004-07-01

Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

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

Technical specifications review of nuclear power plants: a risk-informed evaluation

International Nuclear Information System (INIS)

Saldanha, Pedro Luiz da Cruz; Sousa, Anna Leticia; Frutuoso e Melo, Paulo Fernando Ferreira; Duarte, Juliana Pacheco

2012-01-01

The use of risk information by a regulatory body as part of an integrated decision making process addresses the way in which risk information is being used as part of an integrated process in making decisions about safety issues at nuclear plants – commonly referred to as risk-informed decision making. The risk-informed approach aims to integrate in a systematic manner quantitative and qualitative, deterministic and probabilistic safety considerations to obtain a balanced decision. Probabilistic Safety Assessment (PSA) is a methodology that can be applied to provide a structured analysis process to evaluate the frequency and consequences of accidents scenarios in nuclear power plants. Technical Specifications (TS) are specifications regarding the characteristics of nuclear power plants (variables, systems or components) of overriding importance to nuclear safety and radiation protection, which is an integral part of plant operation authorization. Limiting Conditions of Operation (LCO) are the minimum levels of performance or capacity or operating system components required for the safe operation of nuclear plants, as defined in technical specifications. The Maintenance Rule (MR) is a requirement established by the U. S. Nuclear Regulatory Commission (NRC) to check the effectiveness of maintenance carried out in nuclear plants, and plant configuration control. The control of plant configuration is necessary to verify the impact of the maintenance of a safety device out of service on plant safety. The Electric Power Research Institute (EPRI) has assessed the role of probabilistic safety analysis in the regulation of nuclear power plants with the following objectives: a) to provide utilities with an approach for developing and implementing nuclear power station risk-managed technical specification programs; and b) to complement and supplement existing successful configuration risk management applications such as MR. This paper focuses on the evaluation of EPRI

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.

Waste Isolation Pilot Plant Technical Assessment Team Report

Energy Technology Data Exchange (ETDEWEB)

None, None

2015-03-17

This report provides the results of the Waste Isolation Pilot Plant (WIPP) technical assessment led by the Savannah River National Laboratory and conducted by a team of experts in pertinent disciplines from SRNL and Lawrence Livermore National Laboratory (LLNL), Oak Ridge National Laboratory (ORNL), Pacific Northwest National Laboratory (PNNL), and Sandia National Laboratories (SNL).

Standard technical specifications combustion engineering plants: Bases (Sections 2.0--3.3). Volume 2, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/6 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes

Quarterly report - Swedish Nuclear Power Inspectorate. April - June 1982

International Nuclear Information System (INIS)

1982-01-01

The inspectorate controls the realization of the instructions for the nuclear power plants. During the second quarter of 1982 nine plants have been in operation. Ringhals 4 has started with test runs. Different disturbances of the operation of the plants are reported on diagrams. The security at Studsvik and at the nuclear fuel fabrication of ASEA-Atom is dealt with and minor incidents are described. (G.B.)

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

Directory of Open Access Journals (Sweden)

Ugo Pelay

2017-08-01

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

Technical Safety Appraisal of the Rocky Flats Plant

Energy Technology Data Exchange (ETDEWEB)

Brown, Blake P.

1989-01-01

This report provides the results of a Technical Safety Appraisal (TSA) of the Rocky Flats Plant (RFP) conducted November 14 to 18 and November 28 to December 9, 1988. This appraisal covered the effectiveness and improvements in the RFP safety program across the site, evaluating progress to date against standards of accepted practice. The appraisal included coverage of the timeliness and effectiveness of actions taken in response to the recommendations/concerns in three previous Technical Safety Appraisals (TSAs) of RFP Bldg. 707 conducted in July 1986, Bldgs. 771/774 conducted in October/November 1986, and Bldgs. 776/777 conducted in January/February 1988. Results of this appraisal are given in Section IV for each of 14 technical safety areas at RFP. These results include a discussion, conclusions and any new safety concerns for each technical safety area. Appendix A contains a description of the system for categorizing concerns, and the concerns are tabulated in Appendix B. Appendix C reports on the evaluation of the contractor's actions and the current status of each of the 230 recommendations and concerns contained in the three previous TSA reports.

Independent technical review of the Pinellas Plant

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

This report documents an Independent Technical Review (ITR) of facilities, organizations, plans, activities and various other elements required to successfully transition the Pinellas Plant from Defense Program (DP) funded operation to either community developed reuse or safe deactivation leading to decontamination and decommissioning (D&D). The review was conducted at the request of the Department of Energy (DOE) Deputy Assistant Secretary for Facility Transition and Management (EM-60) and is a consensus of the nine member ITR Team.

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.

Vaal Reefs South uranium plant

International Nuclear Information System (INIS)

Anon.

1979-01-01

The Vaal Reefs mining complex, part of the Anglo American Corporation, is the largest gold and uranium producing complex in the world, being South Africa's principal producer, accounting for about a quarter of the country's uranium production. Vaal Reefs South uranium plant in the Orkney district was recently officially opened by Dr AJA Roux, the retiring president of the Atomic Energy Board and chairman of the Uranium Enrichment Corporation and will increase the country's uranium production. In the field of technology, and particularly processing technology, South Africa has shown the world unprecedented technology achievement in the field of uranium extraction from low grade ores and the development of the unique uranium enrichment process. New technical innovations that have been incorporated in this new plant are discussed

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.

Technical Safety Appraisal of the Pinellas Plant

International Nuclear Information System (INIS)

1991-01-01

This report presents the Technical Safety Appraisal (TSA) of the Pinellas Plant in Pinellas County, Florida. The plant is owned and controlled by the US Department of Energy and operated by General Electric Neutron Devices (GEND). The TSA was performed during the period January 15--31, 1989, in support of a Tiger Team Assessment which occurred during the period January 15 to February 2, 1989. The TSA provided the Safety and Health Subteam input to the Tiger Team Assessment. The completion of the assessment process includes: (1) submission of the Team's preliminary findings and concerns, in a Draft Report, to the Manager, Albuquerque Operations Office and to the site contractors at the conclusion of the onsite assessment; (2) review of the Draft Report for technical and factual accuracy; incorporation of the appropriate review comments, suggested changes, and modifications, as well as input from all interested Program Secretarial Offices; preparation of a draft Action Plan by the Albuquerque Operations Office to address the Concerns, and submittal of that Action Plan through the Program Office to ES ampersand H for their review and comment. The Secretary approved the final Action Plan on December 16, 1990, and directed its implementation. The comments and suggestions of the Program Secretarial Offices, the Operations Office, and the site contractor have been incorporated, as appropriate, in this report prior to its publication

Automation of technical specification monitoring for nuclear power plants

International Nuclear Information System (INIS)

Lin, J.C.; Abbott, E.C.; Hubbard, F.R.

1986-01-01

The complexity of today's nuclear power plants combined with an equally detailed regulatory process makes it necessary for the plant staff to have access to an automated system capable of monitoring the status of limiting conditions for operation (LCO). Pickard, Lowe and Garrick, Inc. (PLG), has developed the first of such a system, called Limiting Conditions for Operation Monitor (LIMCOM). LIMCOM provides members of the operating staff with an up-to-date comparison of currently operable equipment and plant operating conditions with what is required in the technical specifications. LIMCOM also provides an effective method of screening tagout requests by evaluating their impact on the LCOs. Finally, LIMCOM provides an accurate method of tracking and scheduling routine surveillance. (author)

Technical diagnosis of industrial plants with radioisotopes

International Nuclear Information System (INIS)

Hartmann, G.

1984-01-01

A survey is given of the application of radioisotopes in technical diagnosis of industrial plants. Proceeding from the economic importance and the state of the art of radioisotope applications, the principles of tracer techniques are outlined including topical examples of application such as passage of coal through a steam generator, wear in impact crashing of coal, wear and corrosion in pipelines, testing the effective cross section of pipes, and investigations of microstructures. Limits and restrictions of applications are briefly discussed

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.

Comparison of methods applicable to evaluation of nuclear power plant technical specifications

International Nuclear Information System (INIS)

Cho, N.Z.; Bozoki, G.E.; Youngblood, R.W.

1986-01-01

This study compares three probabilistic methods based on the static fault tree analysis, time-dependent unavailability analysis, and Markov analysis, which can be used to evaluate technical specifications in nuclear power plants. They are tested on a sample problem which was devised to closely represent the important and essential characteristics that should be addressed in determination and evaluation of the technical specifications

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.

(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.

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)

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).

Canadian CANDU plant data systems for technical surveillance and analysis

International Nuclear Information System (INIS)

Deverno, M.; Pothier, H.; Xian, C.; Grosbois, J. De; Bosnich, M.

1996-01-01

Plant data systems are emerging as a critical plant support system technology. In particular, plant-wide Historical Data Systems (HDS) are pivotal to the successful implementation of technical surveillance and analysis programs supporting plant operations, maintenance, safety, and licensing activities. In partnership with Canadian CANDU utility and design organizations, AECL has conducted a review of current Canadian CANDU HDS approaches with emphasis on understanding the existing functionality and uses of plant historical data systems, their future needs and benefits. The results is a vision of a plant-wide HDS providing seamless access to both near real-time and historical data, user tool-kits for data visualization and analysis, and data management of the large volume of data acquired during the life of a plant. The successful implementation of the HDS vision will lead to higher capability and capacity factors while minimizing Operations, Maintenance, and Administration (OM and A) costs. (author). 5 refs, 3 figs

Canadian CANDU plant data systems for technical surveillance and analysis

Energy Technology Data Exchange (ETDEWEB)

Deverno, M; Pothier, H; Xian, C [Atomic Energy of Canada Ltd., Control Centre Technology Branch, Fredericton, NB (Canada); Grosbois, J De; Bosnich, M [Atomic Energy of Canada Ltd., Control Centre Technology Branch, Chalk River, ON (Canada). Chalk River Labs.

1997-12-31

Plant data systems are emerging as a critical plant support system technology. In particular, plant-wide Historical Data Systems (HDS) are pivotal to the successful implementation of technical surveillance and analysis programs supporting plant operations, maintenance, safety, and licensing activities. In partnership with Canadian CANDU utility and design organizations, AECL has conducted a review of current Canadian CANDU HDS approaches with emphasis on understanding the existing functionality and uses of plant historical data systems, their future needs and benefits. The results is a vision of a plant-wide HDS providing seamless access to both near real-time and historical data, user tool-kits for data visualization and analysis, and data management of the large volume of data acquired during the life of a plant. The successful implementation of the HDS vision will lead to higher capability and capacity factors while minimizing Operations, Maintenance, and Administration (OM and A) costs. (author). 5 refs, 3 figs.

Standard technical specifications: Combustion engineering plants. Volume 3, Revision 1: Bases (Sections 3.4--3.9)

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Combustion Engineering Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

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.

2. Quarterly progress report, 1983

International Nuclear Information System (INIS)

1983-08-01

This quarterly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 58 Co, 60 Co, 134 Cs, 137 Cs, 90 Sr, 106 Ru, K, 54 Mn, U and T). A bibliographic selection is also presented [fr

3. Quarterly progress report 1982

International Nuclear Information System (INIS)

1982-01-01

This quarterly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 58 Co, 60 Co 134 Cs, 137 Cs, 90 Sr, 106 Ru, K, 54 Mn, U and T). A bibliographic selection is also presented [fr

KWL Lingen nuclear plant. Technical annual report 2016; KWL Kernkraftwerk Lingen. Technischer Jahresbericht 2016

Energy Technology Data Exchange (ETDEWEB)

NONE

2017-07-01

The technical annual report 2016 for KWL (Lingen nuclear plant) covers the following sections: dismantling project management and operation, monitoring and clearance; waste management, technical qualification, security and safety, central tasks; licensing and supervision procedures, operational data, radiation monitoring, radioactive materials, in-service inspections.

XML: Solution for the integration of nuclear power plant data and technical documents

International Nuclear Information System (INIS)

Gordillo, F.

2000-01-01

Assuring proper operation of the systems that make up a nuclear power plant requires handling a massive amount of technical documents. This technical documentation, consisting mainly of system descriptions, operating and maintenance procedures, safety procedures, etc, presents particular characteristics, mainly: Great volume of information. High contents in figures and graphics. High reliability required. Multiple cross-references among documents. (Author)

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.

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.

Technical dictionary power plant engineering. Vol. 1. 4. rev. and enlarged ed.

International Nuclear Information System (INIS)

1987-01-01

This dictionary is a compilation of German and English technical terms of power plant engineering as far as power plants, turbine-generators and assembly engineering are concerned. It is the result of a joint effort by the Kraftwerk Union AG (KWU) and Utility Power Corp. (UPC). The entire content has been revised and approx. 6000 new terms have been added. The dictionary is meant to form a basis for uniform terminology on technical documents as well as correspondence between KWU, UPC and licensees. This computer aided dictionary is printed in capital/low case letters. Only nouns, terms with an article and proper names are capitalized in German. Some terms are written differently in American and British English and are marked with (US) or (GB). (orig./HP) [de

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.

4. Quarterly progress report, 1982

International Nuclear Information System (INIS)

1982-01-01

This quarterly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 58 Co, 60 Co, 134 Cs, 137 Cs, 125 Sb, 90 Sr, 106 Ru, K, 54 Mn, U and T). A bibliographic selection is also presented [fr

Z plant aggregate area management study technical baseline report

International Nuclear Information System (INIS)

DeFord, D.H.; Carpenter, R.W.

1995-05-01

This document was prepared in support of the development of a Aggregate Area Management Study of Z Plant, 200 West Area, at the US Department of Energy (DOE) Hanford Site near Richland, Washington. It provides a technical description and operational history of the aggregate area and results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC) which is currently the Waste Site and Facility Research Office, Natural Resources, Bechtel Hanford, Inc. (BHI). It is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted in support of this report

Technical basis for the internal dosimetry program at the Y-12 Plant

International Nuclear Information System (INIS)

Ashley, J.C.; Barber, J.M.; Snapp, L.M.; Turner, J.E.

1992-01-01

Since the beginning of plant operations. almost all work with radioactive materials has involved isotopes associated with uranium, enriched or depleted in U 235 . While limited quantities of isotopes of elements other than uranium are present, workplace monitoring and precess knowledge have established that internal exposure from these other isotopes is insignificant in comparison with uranium. While the changing plant mission may necessitate the consideration of internal exposure from other isotopes at some point in time, only enriched and depleted uranium will be considered in this basis document. The portions of the internal dosimetry technical basis which may be unique to the Y-12 Plant is considered in this manual. This manual presents the technical basis of the routine in vivo and in vitro bioassay programs including choice of frequency, participant selection criteria, and action level guidelines. Protocols for special bioassay will be presented in the chapters which described the basis for intake, uptake, and dam assessment. A discussion of the factors which led to the need to develop a special biokinetic model for uranium at the Y-12 Plant, as well as a description of the model's basic parameters, are included in this document

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

International Nuclear Information System (INIS)

Koponen, H.

1989-02-01

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

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

International Nuclear Information System (INIS)

Koponen, H.

1988-12-01

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

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

International Nuclear Information System (INIS)

Haenninen, R.

1988-06-01

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

Technical and institutional safety features of nuclear power plants in Brazil

International Nuclear Information System (INIS)

Rosa, L.P.

1986-01-01

This work reports technical, political and institutional safety features of nuclear power plants in Brazil. It is mainly concerned with reactor accidents and personnel safety. The three mile Island and Chernobyl accidents are also discussed and taken as examples. (A.C.A.S.)

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).

Standard technical specifications: Babcock and Wilcox plants. Volume 3, Revision 1: Bases (Sections 3.4--3.9)

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Babcock and Wilcox Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

Technical evaluation of the proposed changes in the technical specifications for emergency power sources for the Big Rock Point nuclear power plant

International Nuclear Information System (INIS)

Latorre, V.R.

1979-12-01

The technical evaluation is presented for the proposed changes to the Technical Specifications for emergency power sources for the Big Rock Point nuclear power plant. The criteria used to evaluate the acceptability of the changes include those delineated in IEEE Std-308-1974, and IEEE Std-450-1975 as endorsed by US NRC Regulatory Guide 1.129

[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.

On the technical superiority of domestic power plant equipment and its development

International Nuclear Information System (INIS)

Zhao Zhiyi

1993-01-01

Under the Presumption of affirmed superiority of domestic power plant equipment, some existing deficiencies are pointed out. The scientific and technical development of domestic power equipment can be impelled through catching up with advanced technologies. The necessity of optimal matching of plant equipment from the engineering point of view is emphasized by the authors in association with a prospective outlook of key power equipment and development suggestions

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

Energy Technology Data Exchange (ETDEWEB)

1981-01-01

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

Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward

Energy Technology Data Exchange (ETDEWEB)

John Collins

2009-01-01

This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

Quarterly report of the Swedish Nuclear Power Inspectorate

International Nuclear Information System (INIS)

1984-01-01

The inspectorate is reporting on the departures of the nuclear power plants from normal operations. No safety incidents of importance occurred during the 4th quarter 1983. There have been 12 reactor trips for the 10 power units, 9 of those occurred on Dec. 27th, when the Southern Swedish power grid tripped.(P.Aa.)

Evaluation of Watts Bar Nuclear Plant Unit 1 Technical Specifications

International Nuclear Information System (INIS)

Baxter, D.E.; Bruske, S.J.

1985-08-01

This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Watts Bar Nuclear Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumption of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Watts Bar T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Watts Bar Nuclear Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

Technical evaluation of RETS-required reports for Crystal River Nuclear Generating Plant, Unit 3, for 1983

International Nuclear Information System (INIS)

Magleby, E.H.; Young, T.E.

1985-01-01

A review was performed on the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at Florida Power Corporation's Crystal River Nuclear Plant, Unit 3, during 1983. The three periodic reports reviewed were (1) the Effluent and Waste Disposal Semiannual Report, January 1-June 30, 1983, (2) the Effluent and Waste Disposal Semiannual Report, July 1-December 31, 1983, and (3) the Annual Environmental Operating Report, Radiological, 1983. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

Advanced Power Ultra-Uprates of Existing Plants (APPU) Final Scientific/Technical Report

Energy Technology Data Exchange (ETDEWEB)

Rubiolo, Pablo R. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Conway, Lawarence E. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Oriani, Luca [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Lahoda, Edward J. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; DeSilva, Greg [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Hu, Min H. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Hartz, Josh [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Bachrach, Uriel [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Smith, Larry [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Dudek, Daniel F. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Toman, Gary J. [Electric Power Research Inst. (EPRI), Palo Alto, CA (United States); Feng, Dandong [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Hejzlar, Pavel [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Kazimi, Mujid S. [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

2006-03-31

This project assessed the feasibility of a Power Ultra-Uprate on an existing nuclear plant. The study determined the technical and design limitations of the current components, both inside and outside the containment. Based on the identified plant bottlenecks, the design changes for major pieces of equipment required to meet the Power Ultra-Uprate throughput were determined. Costs for modified pieces of equipment and for change-out and disposal of the replaced equipment were evaluated. These costs were then used to develop capital, fuel and operating and maintenance cost estimates for the Power Ultra-Uprate plant. The cost evaluation indicates that the largest cost components are the replacement of power (during the outage required for the uprate) and the new fuel loading. Based on these results, the study concluded that, for a standard 4-loop plant, the proposed Power Ultra-Uprate is technically feasible. However, the power uprate is likely to be more expensive than the cost (per Kw electric installed) of a new plant when large capacity uprates are considered (>25%). Nevertheless, the concept of the Power Ultra-Uprate may be an attractive option for specific nuclear power plants where a large margin exists in the steam and power conversion system or where medium power increases (~600 MWe) are needed. The results of the study suggest that development efforts on fuel technologies for current nuclear power plants should be oriented towards improving the fuel performance (fretting-wear, corrosion, uranium load, manufacturing, safety) required to achieve higher burnup rather focusing on potential increases in the fuel thermal output.

Advanced Power Ultra-Uprates of Existing Plants (APPU) Final Scientific/Technical Report

International Nuclear Information System (INIS)

Rubiolo, Pablo R.; Conway, Lawarence E.; Oriani, Luca; Lahoda, Edward J.; DeSilva, Greg; Hu, Min H.; Hartz, Josh; Bachrach, Uriel; Smith, Larry; Dudek, Daniel F.; Toman, Gary J.; Feng, Dandong; Hejzlar, Pavel; Kazimi, Mujid S.

2006-01-01

This project assessed the feasibility of a Power Ultra-Uprate on an existing nuclear plant. The study determined the technical and design limitations of the current components, both inside and outside the containment. Based on the identified plant bottlenecks, the design changes for major pieces of equipment required to meet the Power Ultra-Uprate throughput were determined. Costs for modified pieces of equipment and for change-out and disposal of the replaced equipment were evaluated. These costs were then used to develop capital, fuel and operating and maintenance cost estimates for the Power Ultra-Uprate plant. The cost evaluation indicates that the largest cost components are the replacement of power (during the outage required for the uprate) and the new fuel loading. Based on these results, the study concluded that, for a ''standard'' 4-loop plant, the proposed Power Ultra-Uprate is technically feasible. However, the power uprate is likely to be more expensive than the cost (per Kw electric installed) of a new plant when large capacity uprates are considered (>25%). Nevertheless, the concept of the Power Ultra-Uprate may be an attractive option for specific nuclear power plants where a large margin exists in the steam and power conversion system or where medium power increases (∼600 MWe) are needed. The results of the study suggest that development efforts on fuel technologies for current nuclear power plants should be oriented towards improving the fuel performance (fretting-wear, corrosion, uranium load, manufacturing, safety) required to achieve higher burnup rather focusing on potential increases in the fuel thermal output

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.

Floating natural gas processing plants. Technical ideal or feasible technology

Energy Technology Data Exchange (ETDEWEB)

Backhaus, H

1977-04-01

Realizability of floating natural gas processing plants is decisively influenced by the economy of the system. Illustrated by the example of the natural gas product LPG (liquefied petroleum gas), a model cost calculation is carried out. It is demonstrated that the increase in the price level during the 1973/1974 energy crisis is an important factor for the realiability in terms of economy of such complicated technical systems. Another aspect which the model calculation revealed is that the economy of floating natural gas processing plants and storage systems can only be estimated in connection with other system components.

S Plant Aggregate Area Management study technical baseline report

International Nuclear Information System (INIS)

DeFord, D.H.; Carpenter, R.W.

1995-05-01

This document is prepared in support of an Aggregate Area Management Study of S Plant, 200 West Area, at the US Department of Energy's (DOE) Hanford Site near Richland, Washington. It provides a technical baseline of the aggregate area and the results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC). This document is based on review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. This report describes the REDOX facility and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, underground tank farms designed for high-level liquid wastes, and the lines and encasements that connect them

Wind/photovoltaic power indicators. Fourth quarter 2009; Tableau de bord eolien-photovoltaique. Quatrieme trimestre 2009

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-02-15

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 2010; Tableau de bord eolien-photovoltaique. troisieme trimestre 2010

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

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; Tableau de bord eolien-photovoltaique. Deuxieme trimestre 2011

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

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; Tableau de bord eolien-photovoltaique. troisieme trimestre 2009

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-11-15

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; Tableau de bord eolien-photovoltaique. Deuxieme trimestre 2009

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-09-15

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; Tableau de bord eolien-photovoltaique. Premier trimestre 2011

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

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; Tableau de bord eolien-photovoltaique. Deuxieme trimestre 2010

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

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; Tableau de bord eolien-photovoltaique. Premier trimestre 2010

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

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; Tableau de bord eolien-photovoltaique. Quatrieme trimestre 2010

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

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.)

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.

Restructuring of technical standards for regulation of nuclear power plants in Japan

International Nuclear Information System (INIS)

Takehiko Nakamura; Masahiro Aoki; Kiyoshi Takasaka; Yukio Hirano; Eiji Hiraoka; Mikio Kurihara; Junichi Morita; Zenichi Ogiso; Yoshihiko Nishiwaki

2005-01-01

Regulatory requirements for nuclear power plants (NPPs) have been reviewed and restructured in Japan, in order to accommodate recent technical progress in a timely manner. In this new regulatory process, the governmental technical requirements are modified to performance specifications and the consensus codes and standards established by academic and public societies are being used as prescriptive specifications to realize the performance. As a first step, a fitness-rule to evaluate structural integrity of the components having cracks was introduced into the Japanese regulatory rules in Oct. 2003. 'Rules on Fitness-for-Service for Nuclear Power Plants' by the Japan Society of Mechanical Engineers (JSME) was utilized as a prescriptive specification for in-service-inspections and for the integrity evaluation of the components with stress corrosion cracks and fatigue cracks. The process is being extended to other requirements for structural design and construction of mechanical components and concrete containments, as well as requirements for welding. Prescriptive specifications for the requirements by the JSME and other consensus codes have been technically reviewed by a regulatory body, the Nuclear and Industrial Safety Agency, and specified as regulatory standards for the licensing procedure. In the course of the review, consistency and coverage of the requirements were examined against the Safety Design Guidelines by the Nuclear Safety Commission and the safety requirements for design of nuclear power plant by the International Atomic Energy Agency, NS-R-1. Additional requirements against the stress corrosion cracking, hydrogen accumulation, high-cycle thermal fatigue, etc. are being specified in the requirements to prevent troubles experienced in NPPs in Japan and overseas. This paper describes outlines of the on-going activities restructuring the technical standards for regulation of NPPs in Japan. (authors)

Technical and regulatory challenges for digital instrumentation and control and control room systems in nuclear plants

International Nuclear Information System (INIS)

Torok, R.; Naser, J.; Harris, T.; Keithline, K.

2006-01-01

There are several unsettled technical and licensing issues in the areas of instrumentation and control (I and C), human factors, and updated control room designs that need coordinated, proactive industry attention. Some of these issues are already causing protracted regulatory reviews for existing plants, and left untreated, may cause substantial delays and increased costs for new plant combined construction and operating license approvals. Both industry and the NRC will have roles in resolving the key issues and addressing them in future design efforts and regulatory reviews. Where action is needed, the industry will want to minimize costs and risks by defining industry consensus solutions with corresponding technical bases. NEI has formed a working group to coordinate industry efforts and communications with NRC staff. The working group will also help determine priorities and coordinate both new and existing plant resources. EPRI will provide technical input and guidance for the working group. In order to be able to conduct reviews in a timely fashion, the NRC will likely need to enhance and expand staff resources as existing plants are upgraded and new plant reviews become more active. The industry initiative began with a workshop sponsored by EPRI and NEI on March 28-29, 2006, which led to the creation of the NEI working group. The working group has now identified and prioritized important generic issues, established resolution paths and schedules, and identified the roles of various stakeholders including utility companies, EPRI, NEI, vendors and the NRC. Through the course of this initiative I and C issues for both existing and new plants are being addressed. This paper describes the key I and C related technical and regulatory issues and their implications for new and operating plants, and provides a status report on the efforts to resolve them. (authors)

Technical evaluation of RETS-required reports for the Edwin I. Hatch Nuclear Plant, Units 1 and 2

International Nuclear Information System (INIS)

Young, T.E.; Magleby, E.H.

1985-01-01

A review of the reports required by federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed for the Edwin I. Hatch Nuclear Plant were the Annual Radiological Environmental Operating Report for 1983 and the Semiannual Radioactive Effluent Release Reports for 1983. The principal review guidelines were the plant's specific RETS, NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants'', and NRC Guidance on the Review of the Process Control Programs. The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines. 7 refs

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…

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

Energy Technology Data Exchange (ETDEWEB)

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

1998-10-01

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

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

International Nuclear Information System (INIS)

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

1998-01-01

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

Evaluation of Perry Nuclear Power Plant Unit 1 technical specifications

International Nuclear Information System (INIS)

Baxter, D.E.; Bruske, S.J.

1985-11-01

This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Perry Nuclear Power Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the requirements of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Perry T/S. Several discrepancies were identified and subsequently resolved through telephone conversations with the staff reviewer and the utility representative. Pending completion of the resolutions noted in Parts 3 and 4 of this report, the Perry Nuclear Power Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

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

International Nuclear Information System (INIS)

1990-01-01

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

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)

Standard Technical Specifications General Electric plants, BWR/4:Bases (Sections 3.4-3.10). Volume 3, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the specifications for all chapters and sections of the improved STS. Volume 2 contains he Bases for Chapters 2.0 and 3.0, and Sections 3.1-3.3 of the improved STS. This document, Volume 3, contains the Bases for Sections 3.4-3.10 of the improved STS

Standard Technical Specifications General Electric plants, BWR/4: Bases (Sections 2.0-3.3). Volume 2, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved ST or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume I contains the Specifications for all chapters and sections of the improved STS. This document, Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1-3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4-3.10 of the improved STS

Evaluation of the feasibility, economic impact, and effectiveness of underground nuclear power plants. Final technical report

International Nuclear Information System (INIS)

1978-05-01

Information on underground nuclear power plants is presented concerning underground nuclear power plant concepts; public health impacts; technical feasibility of underground concepts; economic impacts of underground construction; and evaluation of related issues

Standard technical specifications, Westinghouse Plants: Bases (Sections 3.4--3.9). Volume 3, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the Westinghouse Owners Group (WOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency

Standard technical specifications, Westinghouse Plants: Bases (Sections 2.0--3.3). Volume 2, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the Westinghouse Owners Group (WOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency

Wind/photovoltaic power indicators. Third quarter 2011; Tableau de bord eolien-photovoltaique - Troisieme trimestre 2011

Energy Technology Data Exchange (ETDEWEB)

Thienard, Helene

2011-11-15

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, projects in progress, regional status. (J.S.)

Wind/photovoltaic power indicators. Fourth quarter 2011; Tableau de bord eolien-photovoltaique - Quatrieme trimestre 2011

Energy Technology Data Exchange (ETDEWEB)

Thienard, Helene

2012-02-15

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, projects in progress, regional status. (J.S.)

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.

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

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…

Independent technical review of the Mound Plant

Energy Technology Data Exchange (ETDEWEB)

1994-06-01

This report documents an Independent Technical Review (ITR) of the facilities, organizations, plans, and activities required to transition particular elements of the Mound Plant from Defense Program (DP) funded operation as appropriate either to community developed reuse or safe deactivation leading to decontamination and decommissioning (D&D). The review was conducted at the request of the Dr. Willis Bixby, Deputy Assistant Secretary, U.S. Department of Energy EM-60, Office of Facility Transition and Management and is a consensus of the nine member ITR Team. Information for the review was drawn from documents provided to the ITR Team by the Miamisburg Area Office (MB) of the DOE, EG&G, the City of Miamisburg, and others; and from presentations, discussions, interviews, and facility inspections at the Mound Plant during the weeks of March 14 and March 28, 1994. During the week of April 25, 1994, the ITR Team met at Los Alamos, New Mexico to develop consensus recommendations. A presentation of the core recommendations was made at the Mound Plant on May 5, 1994. This is an independent assessment of information available to, and used by, the Mound Plant personnel. Repetition of the information is not meant to imply discovery by the ITR Team. Team members, however, acting as independent reviewers, frequently assess the information from a perspective that differs significantly from that of the Mound Plant personnel. The report is based on information obtained and conditions observed during the March 1994 review interval. The ITR process and normal site work often initiate rapid, beneficial changes in understanding and organization immediately following the review. These changes frequently alter conditions observed during the review, but the report does not address changes subsequent to the review interval.

NEPA Project quarterly progress report, April 1--June 30, 1950

Energy Technology Data Exchange (ETDEWEB)

NONE

1950-12-31

Exploration of various types of power plant cycles for nuclear propelled aircraft has been continued during this quarter. The principal current objective of the project is the development of information which will make an intelligent choice of the basic power plant cycle possible. It is still hoped that this choice can be made late in 1950. The survey studies which have been under way for several months continued during the quarter. These consist of analyses and rough preliminary layouts for various types of aircraft, using each of the several basic cycles which have been seriously considered for each of the three phases of development. Although it is still extremely premature to discuss the relative merits of the various cycles, the information so for developed discloses some cycle differences which may, if confirmed by additional work, be significant. In this respect, there have been no recent major changes in the comparative standings of the cycles.

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

New technical knowledge to be implemented to the revision of rules on pipe wall thinning management for PWR plants

International Nuclear Information System (INIS)

Hirai, Junya; Nakamura, Takao; Amano, Yoichi

2013-01-01

Rules for PWR plant pipe wall thinning management were formulated by the Japan Society of Mechanical Engineers in 2006. Since then thinning management of Japanese PWR plants has been carried out based on this rule. Pipe wall thinning phenomena to be dealt with in this rule have been identified in many piping components of power plants. New technical knowledge has been accumulated since the issuance of 2006 edition. We have formulated these knowledge and information about the thinning phenomena in PWR power plants. Given the history of application of this rule, we have to make our best effort to carry out a study of latest technical knowledge and implement them to the revision of rule and improve pipe wall thinning management. This paper summarizes the new technical knowledge and basis to be implemented to the revision of rules on pipe wall thinning management for PWR plants in Japan. (author)

Development of standard technical report on using and selecting wireless device in nuclear power plants

International Nuclear Information System (INIS)

Koo, I. S.; Hong, S. B.; Cho, J. W.

2011-11-01

1. Purpose · Development of IEC technical report on wireless device using in nuclear power plants 2. Contents · IEC technical reports of draft for circulation and final draft for next planary meeting · Case study on experiment of wireless devices 3. Implementation methods · Preparation of first draft with experts group, its circulation, discussions on the results of the circulation · Organizing three teams such as preparation, reviews and experiment 4. Results · Maintenance cost will be reduced with application of the wireless technologies in nuclear power plants · Commercial wireless devices will be developed before standard is issued

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

International Nuclear Information System (INIS)

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

1997-01-01

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

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.

Technical guidelines for aseismic design of nuclear power plants

International Nuclear Information System (INIS)

Park, Y.J.; Hofmayer, C.H.

1994-06-01

This document is a translation, in its entirety, of the Japan Electric Association (JEA) publication entitled open-quotes Technical Guidelines for Aseismic Design of Nuclear Power Plants - JEAG 4601-1987.close quotes This guideline describes in detail the aseismic design techniques used in Japan for nuclear power plants. It contains chapters dealing with: (a)the selection of earthquake ground motions for a site, (b) the investigation of foundation and bedrock conditions, (c) the evaluation of ground stability and the effects of ground movement on buried piping and structures, (d) the analysis and design of structures, and (e) the analysis and design of equipment and distribution systems (piping, electrical raceways, instrumentation, tubing and HVAC duct). The guideline also includes appendices which summarize data, information and references related to aseismic design technology

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

Hanford Federal Facility Agreement and Consent Order, quarterly progress report, March 31, 1992

International Nuclear Information System (INIS)

1992-05-01

This is the twelfth quarterly report as required by the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1990), established between the US Department of Energy (DOE), the US Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology). The Tri-Party Agreement sets the plan and schedule for achieving regulatory compliance and cleanup of waste sites at the Hanford Site. This report covers progress for the quarter that ended March 31, 1992. Topics covered under technical status include: disposal of tank wastes; cleanup of past-practice units; permitting and closure of treatment, storage, and disposal units; and other tri-party agreement activities and issues

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.

Results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal

International Nuclear Information System (INIS)

Galkin, A.V.; Baldov, A.N.

2001-01-01

In the paper the results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal are presented. Ground for the examination conducting was Health of Nation Programme ratified by the President and a number of Governmental decisions. The special plant is planned in the Mangystau Region. In the framework of feasibility study the data base by the worldwide known technologies was implemented, on reprocessing and experience of radioactive waste disposal. The technical requirements for the special plant construction are determined. The alternative options by structure content and site location of the special plant and radioactive waste disposal are cited

Instrumentation and process control for fossil demonstration plants. Quarterly technical progress report, April--June 1977

Energy Technology Data Exchange (ETDEWEB)

LeSage, L.G.

1977-07-01

Work has been performed on updating the study of the state-of-the-art of instrumentation for Fossil Demonstration Plants (FDP), development of mass-flow and other on-line instruments for FDP, process control analysis for FDP, and organization of a symposium on instrumentation and control for FDP. A Solids/Gas Flow Test Facility (S/GFTF) under construction for instrument development, testing, evaluation, and calibration is described. The development work for several mass-flow and other on-line instruments is described: acoustic flowmeter, capacitive density flowmeter, neutron activation flowmeter and composition analysis system, gamma ray correlation flowmeter, optical flowmeter, and capacitive liquid interface level meter.

A technical learning on the Pressurized Water Nuclear Power Plants using animation

International Nuclear Information System (INIS)

Ito, Hajime; Tomohara, Yasutaka; Kubo, Setsuo; Ninomiya, Toshiaki

2002-01-01

The pressurized water nuclear power generation plants tends to reduce construction of its new plant from viewpoints of recent stabilization in power demand/supply balance, development of new siting points, and so on. And, together with reducing any opportunity to experience at site, generation alternation to younger engineers without such experiences is progressing. In order to carry out technical tradition with high quality , as it is important to understand experiences of troubles and so on as valuable inheritance to apply them to actual use, it can be thought, in doubt, to be one of solving measures to prepare some learning tools applying the newest technology. The Kansai Electric Co., Ltd. Developed a CAD software using animation and 3D pictures using a personal computer which is edited some processes of technical transition on nuclear energy as a reference on a shape of CD ROM as an object from initial period of nuclear power station to present APWR. (G.K.)

Experiences with a technically oriented plant management system; Erfahrungen mit einem technisch orientierten Betriebs-Management-System

Energy Technology Data Exchange (ETDEWEB)

Haffmann, E. [GiS Gesellschaft fuer integrierte Systemplanung mbH, Erlangen (Germany)

2000-07-01

This contribution first deals with the duality of mercantile and technical plant management systems. The following aspects are considered: reasons for and history of this duality; different approaches taken by mercantile and technical plant management systems; differences in the standardisability of mercantile and technical tasks. Dissolution of the duality through coordinated interplay. The author then goes on to explain the most important components of technically oriented maintenance management. These include the collection of technical plant data (with maintenance-relevant data and relations); the establishment of recurring tasks, the commissioning method (involving occupational safety, packaging and evaluation), compilation of manuals, reporting and accompanying plant documentation. The following tools are useful for DP-assisted maintenance: depiction of organisational and operational structures (authorisation system + IBFS application); workflow systems; modelling (data and object models); navigators; form and dialogue generators; integration of external software (project planning, CAD and Office); interface to mercantile systems. Some highlights of the C/S-IBFS were demonstrated in practice at the symposium. [German] Das Referat behandelt zunaechst die Dualitaet von kaufmaennischen und technischen Betriebs-Management-Systemen anhand folgender Aspekte: - Gruende und Historie dieser Dualitaet, - unterschiedliche Loesungsansaetze von kaufmaennischen und technischen Betriebs-Management-Systemen, - unterschiedliche Standardisierbarkeit von kaufmaennischen und technischen Aufgabenstellungen, - Aufloesung der Dualitaet durch koordniertes Zusammenwirken. Sodann werden wichtige Bausteine eines technisch orientierten Instandhaltungs-Managements erlaeutert. Dazu gehoeren die technische Anlagenerfassung (mit instandhaltungsrelevanten Daten und Relationen), die Einrichtung wiederkehrender Aufgaben, das Arbeitsauftragsverfahren (mit Arbeitssicherheit, Paketierung und

Approaches to the safety of future nuclear power plants. Report of a technical committee meeting

International Nuclear Information System (INIS)

1996-09-01

The Technical Committee Meeting on Approaches to Safety of Future Nuclear Power Plants in Different Countries, held from 29 May to 2 June 1995, contributed to this process. Experts from 14 different countries and two international organizations participated in the meeting, which provided the opportunity to exchange information and to review the answers developed to date to these issues (primarily form the IAEA's technical document ''Development of Safety Principles for the Design of Future Nuclear Power Plants'' IAEA-TECDOC-801) and the report of the International Nuclear Safety Advisory Group ''Basic Safety Principles for Nuclear Power Plants'' (INSAG-3). These references were then used as a starting point for answering the question ''to what degree does general agreement (or harmonization) exist on these desired safety approaches for future reactors, and what opportunities remain for further harmonization? 11 refs, 1 tab

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.

Environmental Impact Report from Santa Rita Hydroelectric Power Plant (Minas Gerais State - Brazil): technical strategic for its elaboration

International Nuclear Information System (INIS)

Souza, J.A. de; Marques Neto, F.P.

1989-01-01

The steps for developing the technical strategies used on the elaboration of Environmental Impact Report from Santa Rita Hydroelectric Power Plant, Minas Gerais State, are described, including the influence area, technical requirements, impact identification, technical selection of mitigative measures, impact meaning and strategy for evaluating the identified impacts. (C.G.C.)

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.

Technical Report Cellulosic Based Black Liquor Gasification and Fuels Plant Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Fornetti, Micheal [Escanaba Paper Company, MI (United States); Freeman, Douglas [Escanaba Paper Company, MI (United States)

2012-10-31

The Cellulosic Based Black Liquor Gasification and Fuels Plant Project was developed to construct a black liquor to Methanol biorefinery in Escanaba, Michigan. The biorefinery was to be co-located at the existing pulp and paper mill, NewPage’s Escanaba Paper Mill and when in full operation would: • Generate renewable energy for Escanaba Paper Mill • Produce Methanol for transportation fuel of further refinement to Dimethyl Ether • Convert black liquor to white liquor for pulping. Black liquor is a byproduct of the pulping process and as such is generated from abundant and renewable lignocellulosic biomass. The biorefinery would serve to validate the thermochemical pathway and economic models for black liquor gasification. It was a project goal to create a compelling new business model for the pulp and paper industry, and support the nation’s goal for increasing renewable fuels production and reducing its dependence on foreign oil. NewPage Corporation planned to replicate this facility at other NewPage Corporation mills after this first demonstration scale plant was operational and had proven technical and economic feasibility. An overview of the process begins with black liquor being generated in a traditional Kraft pulping process. The black liquor would then be gasified to produce synthesis gas, sodium carbonate and hydrogen sulfide. The synthesis gas is then cleaned with hydrogen sulfide and carbon dioxide removed, and fed into a Methanol reactor where the liquid product is made. The hydrogen sulfide is converted into polysulfide for use in the Kraft pulping process. Polysulfide is a known additive to the Kraft process that increases pulp yield. The sodium carbonate salts are converted to caustic soda in a traditional recausticizing process. The caustic soda is then part of the white liquor that is used in the Kraft pulping process. Cellulosic Based Black Liquor Gasification and Fuels Plant project set out to prove that black liquor gasification could

Nuclear heat generating plants - technical concepts and market potentials. Chapter 11

International Nuclear Information System (INIS)

Hasenkopf, O.; Erhard, W.D.; Nonnenmacher, A.; Hanselmann, M.

1988-01-01

Within the framework of a case study under the Federal Ministry of Research and Technology project 'Nuclear heat generating plants - technological concepts and market potentials', the possible applications of such plants were studied giving the district heat supply network of the Technische Werke der Stadt Stuttgart AG (Technical Works of the City of Stuttgart, Inc.) as an example. The use of district heating systems concentrated specifically on areas identified for economical supply because of their topographical position, existing heat density, distance from power plants, and a reasonable delimination from the available gas network. Based on the results of optimization calculations made by the Stuttgart Institute for Nuclear Technology and Energy Conversion, the required investment capital can be estimated as a function of the amount of fuel savings under the Stuttgart case study. (orig./UA) [de

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.

Computation code TEP 1 for automated evaluation of technical and economic parameters of operation of WWER-440 nuclear power plant units

International Nuclear Information System (INIS)

Zadrazil, J.; Cvan, M.; Strimelsky, V.

1987-01-01

The TEP 1 program is used for automated evaluation of the technical and economic parameters of nuclear power plant units with WWER-440 reactors. This is an application program developed by the Research Institute for Nuclear Power Plants in Jaslovske Bohunice for the KOMPLEX-URAN 2M information system, delivered by the USSR to the V-2 nuclear power plants in Jaslovske Bohunice and in Dukovany. The TEP 1 program is written in FORTRAN IV and its operation has two parts. First the evaluation of technical and economic parameters of operation for a calculation interval of 10 mins and second, the control of the calculation procedure, follow-up on input data, determination of technical and economic parameters for a lengthy time interval, and data printout and storage. The TEP 1 program was tested at the first unit of the V-2 power plant and no serious faults appeared in the process of the evaluation of technical and economic parameters. A modification of the TEP 1 programme for the Dukovany nuclear power plant is now being tested on the first unit of the plant. (Z.M.)

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)

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.

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1994-03-01

In the third quarter of 1993, all of Finland's four nuclear power plant units were in power operation, with the exception of the annual maintenance outages of the Loviisa units. The load factor average of the plant units was 83.6 %. None of the events which occurred during this annual quarter had any bearing on nuclear or radiation safety. (4 figs., 5 tabs.)

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1992-05-01

The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost the whole fourth quarter of 1991. The load factor average was 94.7 % (the whole year 90.9 %). All the events in the last annual quarter, which are classified on the International Nuclear Event Scale, were below scale/level 0. Also the events which occurred in the other quarters of the year 1991 were rated at the scale's lowest levels. Occupational radiation doses and releases of radioactive material off-site remained well below authorised limits. Only quantities of radioactive material insignificant to radiation exposure originating in nuclear power plants were detected in the samples collected in the vicinity of the nuclear power plants

Technical basis for external dosimetry at the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

Bradley, E.W.; Wu, C.F.; Goff, T.E.

1993-01-01

The WIPP External Dosimetry Program, administered by Westinghouse Electric Corporation, Waste Isolation Division, for the US Department of Energy (DOE), provides external dosimetry support services for operations at the Waste Isolation Pilot Plant (WIPP) Site. These operations include the receipt, experimentation with, storage, and disposal of transuranic (TRU) wastes. This document describes the technical basis for the WIPP External Radiation Dosimetry Program. The purposes of this document are to: (1) provide assurance that the WIPP External Radiation Dosimetry Program is in compliance with all regulatory requirements, (2) provide assurance that the WIPP External Radiation Dosimetry Program is derived from a sound technical base, (3) serve as a technical reference for radiation protection personnel, and (4) aid in identifying and planning for future needs. The external radiation exposure fields are those that are documented in the WIPP Final Safety Analysis Report

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.

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.

Technical concepts of further improvement of nuclear power plant safety

International Nuclear Information System (INIS)

Sochor, R.

1983-01-01

The following technical concepts are described which secure the integrity of the containment in case of an accident whose scale exceeds the so-called design basis accident: siting nuclear power plants underground which raises construction costs by 20 - 25%; completing the containment with equipment preventing the outflow of molten corium; completing the containment with emergency pressure space for discharging overpressure - this emergency space is filled with gravel which will trap approximately 50% of fission waste. (Ha)

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.

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1991-08-01

In the Quarterly Reports on the operation of the Finnish nuclear power plants such events and observations are described relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Also other events of general interest are reported. The report also includes a summary of the radiation safety of the plants' workers and the environment, as well as tabulated data on the production and load factors of the plants. The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in commercial operation during the whole first quarter of 1991. The load factor average was 99.1 %. Failures have been detected in the uppermost spacing lattices of nuclear fuel bundles removed from the Loviisa nuclear reactors. Further investigations into the significance of the failures have been initiated. In this quarter, renewed cooling systems for the instrumentation area were introduced at Loviisa 1. The modifications made in the systems serve to ensure reliable cooling of the area even during the hottest summer months when the possibility exists that the temperature of the automation equipment could rise too high causing malfunctions which could endanger plant safety. Occupational radiation doses and external releases of radioactivity were below prescribed limits in this quarter. Only small amounts of radioactive substances originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

NST Quarterly - January 1999 issue

International Nuclear Information System (INIS)

1999-01-01

NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights MINT activities in radioactive tracer technique and medical services. Special report on the sediment tracing technique to study the sedimentation pattern at the power stations was presented. The syopsis on two new book launched by MINT also were reviewed. The books are Research Highlights on the Use of Induced Mutations for Plant Improvement in Malaysia and Rice Agro-Ecosystem of the Muda Irrigation Scheme, Malaysia. In medical services, MINT has a group, provide medical physics services such as QA checks on the country's diagnostic radiology equipment and related services

Risk based optimization of technical specifications for operation of nuclear power plants

International Nuclear Information System (INIS)

1993-12-01

The objective of the report is to present an overview of the risk and reliability based approaches (using a probabilistic safety assessment (PSA)) for improving nuclear power plant technical specifications (TS). In that case, it will provide an information base to the Member States in seeking PSA based applications to enhance the effectiveness of their technical specifications. To achieve this objective, the report discusses the basic objectives and reasons for seeking TS changes, the methods, data requirements and uses of different types of applications, and an overview of different applications that have been completed, including detailed descriptions of selected applications. Refs, figs and tabs

Conceptual design of small-sized HTGR system (4). Plant design and technical feasibility

International Nuclear Information System (INIS)

Ohashi, Hirofumi; Sato, Hiroyuki; Yan, Xing L.; Sumita, Junya; Nomoto, Yasunobu; Tazawa, Yujiro; Noguchi, Hiroki; Imai, Yoshiyuki; Tachibana, Yukio

2013-09-01

Japan Atomic Energy Agency (JAEA) has started a conceptual design of a 50MWt small-sized high temperature gas cooled reactor (HTGR) for steam supply and electricity generation (HTR50S), which is a first-of-kind of the commercial plant or a demonstration plant of a small-sized HTGR system for steam supply to the industries and district heating and electricity generation by a steam turbine, to deploy in developing countries in the 2020s. HTR50S was designed for steam supply and electricity generation by the steam turbine with the reactor outlet temperature of 750degC as a reference plant configuration. On the other hand, the intermediate heat exchanger (IHX) will be installed in the primary loop to demonstrate the electricity generation by the helium gas turbine and hydrogen production by thermochemical water splitting by utilizing the secondary helium loop with the reactor outlet temperature of 900degC as a future plant configuration. The plant design of HTR50S for the steam supply and electricity generation was performed based on the plant specification and the requirements for each system taking into account for the increase of the reactor outlet coolant temperature from 750degC to 900degC and the installation of IHX. The technical feasibility of HTR50S was confirmed because the designed systems (i.e., reactor internal components, reactor pressure vessel, vessel cooling system, shutdown cooling system, steam generator (SG), gas circulator, SG isolation and drainage system, reactor containment vessel, steam turbine and heat supply system) satisfies the design requirements. The conceptual plant layout was also determined. This paper provides the summary of the plan design and technical feasibility of HTR50S. (author)

Catalogue and classification of technical safety rules for light-water reactors and reprocessing plants

International Nuclear Information System (INIS)

Bloser, M.; Fichtner, N.; Neider, R.

1975-08-01

This report on the cataloguing and classification of technical rules for land-based light-water reactors and reprocessing plants contains a list of classified rules. The reasons for the classification system used are given and discussed

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.

New technical knowledge to be implemented to the revision of rules on pipe wall thinning management for PWR Plants. 2006 edition

International Nuclear Information System (INIS)

Hirai, Junya; Amano, Yoichi; Nakamura, Takao

2013-01-01

Rules for PWR plant pipe wall thinning management were formulated by the Japan Society of Mechanical Engineers in 2006. Since then thinning management of Japanese PWR plants has been carried out based on this rule. Pipe wall thinning phenomena to be dealt with in this rule have been identified in many piping components of power plants. New technical knowledge has been accumulated since the issuance of 2006 edition. We have formulated these knowledge and information about the thinning phenomena in PWR power plants. Given the history of application of this rule, we have to make our best effort to carry out a study of latest technical knowledge and implement them to the revision of rule and improve pipe wall thinning management. This paper summarizes the new technical knowledge and basis to be implemented to the revision of rules on pipe wall thinning management for PWR plants in Japan. (author)

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1991-02-01

During the third quarter of 1990 the Finnish nuclear power plant units Loviisa 1 and 2 and TVO I and II were in commercial operation for most of the time. The annual maintenance outages of the Loviisa plant units were held during the report period. All events during this quarter are classified as Level hero (Below Scale) on the International Nuclear Event Scale. Occupational radiation doses and external releases of radioactivity were below authorised limits. Only small amounts of radioactive substances originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

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...

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.

Interim technical evaluation report of testing procedures for activated carbon adsorbers in ventilation filter assemblies in nuclear power plants

International Nuclear Information System (INIS)

Sill, C.W.; Scarpellino, C.D.; Tkachyk, J.W.; Grey, A.E.; Frank, C.W.

1985-05-01

Laboratory analysis of activated carbon is required by nuclear power plant technical specifications for use in Engineered Safety Feature (ESF) ventilation systems to determine the capability of those systems to remove radioiodines from air during normal operation and following a design basis accident (DBA). The lask of agreement of laboratory results from a recent round robin raised concerns regarding the adequacy of the analyses, using the ASTM D3803-79 standard, to assure compliance with plant technical specifications. EG and G Idaho was contracted by the NRC to conduct a program to provide the bases for resolving these concerns. This EG and G report serves as an interim Technical Evaluation Report (TER) of the program and presents reviews of the ASTM D3803-79 standard and the commercial testing laboratories. Results of EG and G laboratory studies and the NRC/EG and G Interlaboratory Comparison are presented with conclusions and recommendations concerning changes required to improve the standard and its application. Possible revisions to plant technical specifications required to reflect the true capability of activated carbon to remove radioiodines are also presented

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.

B Plant aggregate area management study technical baseline report

International Nuclear Information System (INIS)

DeFord, D.H.; Carpenter, R.W.

1995-05-01

The B aggregate area is made up of 13 operable units; 200-BP 1 through 200-BP 1 1, 200-IU-6, and 200-SS-1 that consist of liquid and solid waste disposal sites in the vicinity of, and related to, B Plant operations. This report describes B Plant and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches and ditches, ponds, catch tanks, settling tanks, diversion boxes, underground tank farms designed for high-level liquid wastes, and the lines and encasements that connect them. Each waste site in the aggregate area is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. This document provides a technical baseline of the aggregate area and results from an environmental investigation. This document is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted

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.

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

Science.gov (United States)

Selwitz, Jason Lawrence

2017-01-01

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

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.

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1993-09-01

Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear safety and radiation protection which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Safety-enhancing modifications at the nuclear power plants and issues relating to the use of nuclear energy which are of general interest are also reported. The reports include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the first quarter of 1993, a primary feedwater system pipe break occurred at Loviisa 2, in a section of piping after a feedwater pump. The break was erosion-corrosion induced. Repairs and inspections interrupted power generation for seven days. On the International Nuclear Event Scale the event is classified as a level 2 incident. Other events in the first quarter of 1993 had no bearing on nuclear safety and radiation protection

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

International Nuclear Information System (INIS)

Groom, S.H.

1994-01-01

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

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.

Technical analysis of advanced wastewater-treatment systems for coal-gasification plants

Energy Technology Data Exchange (ETDEWEB)

1981-03-31

This analysis of advanced wastewater treatment systems for coal gasification plants highlights the three coal gasification demonstration plants proposed by the US Department of Energy: The Memphis Light, Gas and Water Division Industrial Fuel Gas Demonstration Plant, the Illinois Coal Gasification Group Pipeline Gas Demonstration Plant, and the CONOCO Pipeline Gas Demonstration Plant. Technical risks exist for coal gasification wastewater treatment systems, in general, and for the three DOE demonstration plants (as designed), in particular, because of key data gaps. The quantities and compositions of coal gasification wastewaters are not well known; the treatability of coal gasification wastewaters by various technologies has not been adequately studied; the dynamic interactions of sequential wastewater treatment processes and upstream wastewater sources has not been tested at demonstration scale. This report identifies key data gaps and recommends that demonstration-size and commercial-size plants be used for coal gasification wastewater treatment data base development. While certain advanced treatment technologies can benefit from additional bench-scale studies, bench-scale and pilot plant scale operations are not representative of commercial-size facility operation. It is recommended that coal gasification demonstration plants, and other commercial-size facilities that generate similar wastewaters, be used to test advanced wastewater treatment technologies during operation by using sidestreams or collected wastewater samples in addition to the plant's own primary treatment system. Advanced wastewater treatment processes are needed to degrade refractory organics and to concentrate and remove dissolved solids to allow for wastewater reuse. Further study of reverse osmosis, evaporation, electrodialysis, ozonation, activated carbon, and ultrafiltration should take place at bench-scale.

Establishment of the technical basis to apply the viscous damper in nuclear power plant

International Nuclear Information System (INIS)

Nakajima, J.; Suezono, N.; Higuchi, T.; Katayama, H.

2014-01-01

In recent years, the technical development of the damper using viscous fluid (hereinafter called 'the viscous damper') for the structures, bridges and components in the general industrial field is remarkable, and the experiences of the application to mitigate influence in an earthquake is being gathered now. In this paper, purpose of the whole activity, schedule, the research and test results carried out so far, and future plan to establish the technical basis to apply the viscous damper in nuclear power plant are reported. (author)

Establishment of the technical basis to apply the viscous damper in nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Nakajima, J.; Suezono, N.; Higuchi, T. [Toshiba Corp., Isogo Nuclear Engineering Center, Isogo-ku, Yokohama (Japan); Katayama, H. [Toshiba Corp., Power and Industrial Systems Research and Development Center, Isogo-ku, Yokohama (Japan)

2014-07-01

In recent years, the technical development of the damper using viscous fluid (hereinafter called 'the viscous damper') for the structures, bridges and components in the general industrial field is remarkable, and the experiences of the application to mitigate influence in an earthquake is being gathered now. In this paper, purpose of the whole activity, schedule, the research and test results carried out so far, and future plan to establish the technical basis to apply the viscous damper in nuclear power plant are reported. (author)

Proceedings of a NEA/CSNI-UNIPEDE specialist meeting on improving technical specifications for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

1987-07-01

This CSNI specialist meeting on improving technical specifications for nuclear power plants is sponsored by the OECD Nuclear Energy Agency jointly with UNIPEDE. Technical specifications for nuclear power plants are in a way a prescription which has a direct bearing on the success or failure of the particular installation, and on the success or failure of fission energy around the world. It is therefore highly important that these prescriptions are made as clear and as concise as possible and that it distinguishes requirements which are essential for public health and safety, from the many others which are less important accordingly. The conference was held in september 1987 in madrid (Spain); it is composed of about 40 papers grouped into 8 sessions: invited papers (6 papers), international survey results (1 paper), limiting conditions for operation (8 papers), maintenance and testing (4 papers), actions statements and allowed outage times (8 papers), methodology and technical justification (8 papers), future trends and alternative approaches (4 papers), and a final panel

Cycle water chemistry based on film forming amines at power plants: evaluation of technical guidance documents

Science.gov (United States)

Dyachenko, F. V.; Petrova, T. I.

2017-11-01

Efficiency and reliability of the equipment in fossil power plants as well as in combined cycle power plants depend on the corrosion processes and deposit formation in steam/water circuit. In order to decrease these processes different water chemistries are used. Today the great attention is being attracted to the application of film forming amines and film forming amine products. The International Association for the Properties of Water and Steam (IAPWS) consolidated the information from all over the World, and based on the research studies and operating experience of researchers and engineers from 21 countries, developed and authorized the Technical Guidance Document: “Application of Film Forming Amines in Fossil, Combined Cycle, and Biomass Power Plants” in 2016. This article describe Russian and International technical guidance documents for the cycle water chemistries based on film forming amines at fossil and combined cycle power plants.

Relaxation of inservice test frequency requirement for Kori 1 ASME code pumps

International Nuclear Information System (INIS)

Sohn, Gap Heon; Choi, Hae Yoon; Min, Kyung Sung; Rim, Nam Jin

1994-08-01

The objective of this investigation is to evaluate the technical and regulational requirements to justify the relaxation of the test frequency of Kori 1 pumps through reviewing the related rules and codes and standards, technical specifications of Kori 1 and other similar plants, standard technical specifications, research results for tech. spec. improvements and site test records. It is concluded that the relaxation of test frequency to quarterly be justified based on the conformance with rules and codes and standard, quarterly test cases in similar plants and standard tech. spec., recommendations of research result and stable site test records. (Author) 16 refs., 26 figs., 13 tabs

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)

Standard technical specifications - Babcock and Wilcox Plants: Bases (Sections 2.0-3.3). Volume 2, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This NUREG contains the improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the B ampersand W Owners Group (BWOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency

Technical and economical prerequisites of special district-heating nuclear power plant development

International Nuclear Information System (INIS)

Baturov, B.B.; Boldyrev, V.M.; Losev, V.L.; Sigal, M.V.

1983-01-01

Results are presented of technical and economical analysis of advisability of constructing combined Nuclear Power and Heating Plants (NPHP) assuring the possibility of their location near the areas of heat power consumption in case of observing a given degree of radiation safety for population and personnel. Specific features determining the choice of turbine-driven units for such plants are analyzed. Conditions of competiveness of a specialized NPHP with alternative power units, NPHP based on the WWER-1000 reactor and district heating plants (NDHP), are determined. Analysis of design specifications of NPHP with two VK-500 reactor units and structures of capital investments in such a plant reveal that an increase in the total capital investments in the NPHP would not exceed 2% with account of the difference in costs for grid heaters and a corresponding change in dimensions of operation rooms as well as changes in costs of heat removal system (within one site) at the TK turbine replacement by the T turbine

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

Energy supply the 4th quarter and the whole years 2000 and 2001, corrected version. Preliminary data

International Nuclear Information System (INIS)

2002-01-01

The objective of the presented statistics is to give a total picture of the Swedish energy supply and its development. The efficiency of the final consumption is not considered in the balance sheets. The quantities (recalculated to tera joules = 10 12 joules) as reported under final consumption refer only to the total energy delivered to the consumers. The final consumption of energy in Sweden the 4th quarter 2001 increased by 5 per cent compared to the corresponding period 2000. The rise can be explained with the fact that the 4th quarter 2001 was colder compared with the same quarter 2000. The consumption within industrial sector was unchanged although the consumption within transports diminished. During the year 2001 energy consumption was unchanged compared with the year 2000. The consumption in household and service sector rose by 8 per cent. The highest rise can be find in the use of district heating and domestic fuels. The industry sector used 5 per cent less energy and mainly in the use of electric energy and domestic fuels. The gross supply of energy in Sweden the 4th quarter increased by 3,5 per cent compared to the 4th quarter 2000. The production of electricity from nuclear plants was 23 per cent higher compared with the same quarter 2000. Hydro-electric power production decreased by 4 per cent during the same period. The supply of natural gas rose by 24 per cent and the supply of domestic fuels rose by 4 %, the supply of coal and coke increased by 3 per cent and the same increase occurred in the supply of oil products. The gross supply of energy was 3 per cent higher during 2001 compared with 2000. The increase can be seen in the supply of coal and coke, 7 per cent, natural gas, 15 per cent, and production of electric energy in nuclear plants, 26 per cent. The balance sheets give both the total flow of various sources of energy and specifications of conversion and consumption in the energy producing industries. The contents of the balance sheets are

Technical methods for a risk-informed, performance-based fire protection program at nuclear power plants

International Nuclear Information System (INIS)

Dey, M.K.

1998-01-01

This paper presents a technical review and examination of technical methods that are available for developing a risk-informed, performance-based fire protection program at a nuclear plant. The technical methods include ''engineering tools'' for examining the fire dynamics of fire protection problems, reliability techniques for establishing an optimal fire protection surveillance program, fire computer codes for analyzing important fire protection safety parameters, and risk-informed approaches that can range from drawing qualitative insights from risk information to quantifying the risk impact of alternative fire protection approaches. Based on this technical review and examination, it is concluded that methods for modeling fires, and reliability and fire PRA analyses are currently available to support the initial implementation of simple risk-informed, performance-based approaches in fire protection programs. (author)

Technical methods for a risk-informed, performance-based fire protection program at nuclear power plants

International Nuclear Information System (INIS)

Dey, M.K.

2000-01-01

This paper presents a technical review and examination of technical methods that are available for developing a risk-informed, performance-based fire protection program at a nuclear plant. The technical methods include 'engineering tools' for examining the fire dynamics of fire protection problems, reliability techniques for establishing an optimal fire protection surveillance program, fire computer codes for analyzing important fire protection safety parameters, and risk-informed approaches that can range from drawing qualitative insights from risk information to quantifying the risk impact of alternative fire protection approaches. Based on this technical review and examination, it is concluded that methods for modeling fires, and reliability and fire probabilistic risk analyses (PRA) are currently available to support the initial implementation of simple risk-informed, performance-based approaches in fire protection programs. (orig.) [de

Technical knowledge/skill transfer in nuclear power plant manufacturer

International Nuclear Information System (INIS)

Arima, Hiroshi; Sagawa, Wataru; Ogawa, Yukio

2009-01-01

Due to environmental concerns such as global warming, needs for nuclear power is increasing. However, many expert engineers and technicians are now entering a period of retirement. And due to weak demands of new plant construction for long years, opportunity for technology learning/experience had been lost. Therefore, to secure human resource and to develop their ability are urgent issues for nuclear industries. Hitachi nuclear division continues efforts for technology transfer and human resource training. This paper describes the following two activities. (1) Improvement of common technical basis, and implementation of PDCA cycle, (2) Development of supporting tools to accelerate technology transfer through OJT (On the Job Training). (author)

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

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.

[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

A COMPUTATIONAL WORKBENCH ENVIRONMENT FOR VIRTUAL POWER PLANT SIMULATION

International Nuclear Information System (INIS)

Mike Bockelie; Dave Swensen; Martin Denison

2002-01-01

This is the fifth Quarterly Technical Report for DOE Cooperative Agreement No: DE-FC26-00NT41047. The goal of the project is to develop and demonstrate a computational workbench for simulating the performance of Vision 21 Power Plant Systems. Within the last quarter, our efforts have become focused on developing an improved workbench for simulating a gasifier based Vision 21 energyplex. To provide for interoperability of models developed under Vision 21 and other DOE programs, discussions have been held with DOE and other organizations developing plant simulator tools to review the possibility of establishing a common software interface or protocol to use when developing component models. A component model that employs the CCA protocol has successfully been interfaced to our CCA enabled workbench. To investigate the software protocol issue, DOE has selected a gasifier based Vision 21 energyplex configuration for use in testing and evaluating the impacts of different software interface methods. A Memo of Understanding with the Cooperative Research Centre for Coal in Sustainable Development (CCSD) in Australia has been completed that will enable collaborative research efforts on gasification issues. Preliminary results have been obtained for a CFD model of a pilot scale, entrained flow gasifier. A paper was presented at the Vision 21 Program Review Meeting at NETL (Morgantown) that summarized our accomplishments for Year One and plans for Year Two and Year Three

Investigative study on the technical code requirements of natural events hazards for nuclear power plants

International Nuclear Information System (INIS)

Ito, Kunio; Aoki, Takayuki

2012-01-01

Technical codes and standards on natural phenomena, in particular, earthquake and tsunami for nuclear power plants in the other developed countries including IAEA safety standards were investigated. Then, the results were compared with the corresponding Japanese technical codes and standards. As a results, it was found that: (1) technical codes and standards on natural phenomena, especially those for earthquakes and tsunami/flooding in those foreign countries and their requirements are all included in the Japanese technical codes and standards. (2) Nevertheless, the actual measures against tsunami/flooding in those foreign countries are more advanced than those in Japan which had been taken before Fukushima accident. Therefore, further investigation is needed to clarify the reason why there are such differences by investigating the details of the basic ideas and evaluation methods for the protection of tsunami/flooding. (author)

Technical Proposal Salton Sea Geothermal Power Pilot Plant Program

Energy Technology Data Exchange (ETDEWEB)

None

1975-03-28

The proposed Salton Sea Geothermal Power Pilot Plant Program comprises two phases. The objective of Phase 1 is to develop the technology for power generation from high-temperature, high-salinity geothermal brines existing in the Salton Sea known geothermal resources area. Phase 1 work will result in the following: (a) Completion of a preliminary design and cost estimate for a pilot geothermal brine utilization facility. (b) Design and construction of an Area Resource Test Facility (ARTF) in which developmental geothermal utilization concepts can be tested and evaluated. Program efforts will be divided into four sub-programs; Power Generation, Mineral Extraction, Reservoir Production, and the Area Resources Test Facility. The Power Generation Subprogram will include testing of scale and corrosion control methods, and critical power cycle components; power cycle selection based on an optimization of technical, environmental and economic analyses of candidate cycles; preliminary design of a pilot geothermal-electric generating station to be constructed in Phase 2 of this program. The Mineral Extraction Subprogram will involve the following: selection of an optimum mineral recovery process; recommendation of a brine clean-up process for well injection enhancement; engineering, construction and operation of mineral recovery and brine clean-up facilities; analysis of facility operating results from environmental, economical and technical point-of-view; preliminary design of mineral recovery and brine clean-up facilities of sufficient size to match the planned pilot power plant. The Reservoir Production Subprogram will include monitoring the operation and maintenance of brine production, handling and injection systems which were built with private funding in phase 0, and monitoring of the brine characteristics and potential subsidence effects during well production and injection. Based on the above, recommendations and specifications will be prepared for production and

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.

Method for assessment of the technical potential of the plant agricultural waste suitable for energy purposes in Bulgaria

International Nuclear Information System (INIS)

Georgiev, V.

2004-01-01

A method for assessment of technical potential of quantitatively important plant agriculture waste; straw from wheat and barley; corn stalks; sunflower stalks and heads; tobacco stalks; orchard prunings and vineyard prunings suitable for energy purposes for Bulgarian conditions is developed. Data for assessment of the technical potential for 2002 using this method are presented. A comparison between technical potential of mentioned wastes, final energy consumption in agriculture and all branches of Bulgarian economy for 2002 is made. (author)

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).

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

Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 31, 1956, Part 1 - 5

Energy Technology Data Exchange (ETDEWEB)

Jordan, W. H. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Cramer, S. J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Miller, A. J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

1957-03-12

This quarterly progress report of the Aircraft Nuclear Propulsion Project at ORNL records the technical progress of the research on circulating-fuel reactors and other ANP research at the Laboratory under its Contract W-7405-eng-26. The report is divided into five major parts: 1. Aircraft Reactor Engineering, 2. Chemistry, 3. Metallurgy, 4. Heat Transfer and Physical Properties, Radiation Damage, and Fuel Recovery and Reprocessing, and 5. Reactor Shielding. The ANP Project is comprised of about 550 technical and scientific personnel engaged in many phases of research directed toward the achievement of nuclear propulsion of aircraft. A considerable portion of this research is performed in support of the work of other organizations participating in the national ANP effort. However, the bulk of the ANP research at ORNL is directed toward the development of a circulating-fuel type of reactor. The design, construction, and operation of the Aircraft Reactor Test (ART), with the cooperation of the Pratt & Whitney Aircraft Division, are the current objectives of the project. The ART is to be a power plant system that will include a 60-Mw circulating fuel reflector-moderator reactor and adequate means for heat disposal. Operation of the system will be for the purpose of determining feasibility and for studying the problems associated with the design, construction, and operation of a high-power circulating-fuel refIector-moderated aircraft reactor system.

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.

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.

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

An Evaluation of the Plant Density Estimator the Point-Centred Quarter Method (PCQM Using Monte Carlo Simulation.

Directory of Open Access Journals (Sweden)

Md Nabiul Islam Khan

Full Text Available In the Point-Centred Quarter Method (PCQM, the mean distance of the first nearest plants in each quadrant of a number of random sample points is converted to plant density. It is a quick method for plant density estimation. In recent publications the estimator equations of simple PCQM (PCQM1 and higher order ones (PCQM2 and PCQM3, which uses the distance of the second and third nearest plants, respectively show discrepancy. This study attempts to review PCQM estimators in order to find the most accurate equation form. We tested the accuracy of different PCQM equations using Monte Carlo Simulations in simulated (having 'random', 'aggregated' and 'regular' spatial patterns plant populations and empirical ones.PCQM requires at least 50 sample points to ensure a desired level of accuracy. PCQM with a corrected estimator is more accurate than with a previously published estimator. The published PCQM versions (PCQM1, PCQM2 and PCQM3 show significant differences in accuracy of density estimation, i.e. the higher order PCQM provides higher accuracy. However, the corrected PCQM versions show no significant differences among them as tested in various spatial patterns except in plant assemblages with a strong repulsion (plant competition. If N is number of sample points and R is distance, the corrected estimator of PCQM1 is 4(4N - 1/(π ∑ R2 but not 12N/(π ∑ R2, of PCQM2 is 4(8N - 1/(π ∑ R2 but not 28N/(π ∑ R2 and of PCQM3 is 4(12N - 1/(π ∑ R2 but not 44N/(π ∑ R2 as published.If the spatial pattern of a plant association is random, PCQM1 with a corrected equation estimator and over 50 sample points would be sufficient to provide accurate density estimation. PCQM using just the nearest tree in each quadrant is therefore sufficient, which facilitates sampling of trees, particularly in areas with just a few hundred trees per hectare. PCQM3 provides the best density estimations for all types of plant assemblages including the repulsion process

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 ...

Risk-based technical specifications: Development and application of an approach to the generation of a plant specific real-time risk model

International Nuclear Information System (INIS)

Puglia, B.; Gallagher, D.; Amico, P.; Atefi, B.

1992-10-01

This report describes a process developed to convert an existing PRA into a model amenable to real time, risk-based technical specification calculations. In earlier studies (culminating in NUREG/CR-5742), several risk-based approaches to technical specification were evaluated. A real-time approach using a plant specific PRA capable of modeling plant configurations as they change was identified as the most comprehensive approach to control plant risk. A master fault tree logic model representative of-all of the core damage sequences was developed. Portions of the system fault trees were modularized and supercomponents comprised of component failures with similar effects were developed to reduce the size of the model and, quantification times. Modifications to the master fault tree logic were made to properly model the effect of maintenance and recovery actions. Fault trees representing several actuation systems not modeled in detail in the existing PRA were added to the master fault tree logic. This process was applied to the Surry NUREG-1150 Level 1 PRA. The master logic mode was confirmed. The model was then used to evaluate frequency associated with several plant configurations using the IRRAS code. For all cases analyzed computational time was less than three minutes. This document Volume 2, contains appendices A, B, and C. These provide, respectively: Surry Technical Specifications Model Database, Surry Technical Specifications Model, and a list of supercomponents used in the Surry Technical Specifications Model

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

IMPROVEMENT OF SYSTEMS OF TECHNICAL WATER SUPPLY WITH COOLING TOWERS FOR HEAT POWER PLANTS TECHNICAL AND ECONOMIC INDICATORS PERFECTION. Part 2

Directory of Open Access Journals (Sweden)

Yu. A. Zenovich-Leshkevich-Olpinskiy

2016-01-01

Full Text Available The method of calculation of economic efficiency that can be universal and is suitable for feasibility study of modernization of irrigation and water distribution system of cooling towers has been developed. The method takes into account the effect of lower pressure exhaust steam in the condenser by lowering the temperature of the cooling water outlet of a cooling tower that aims at improvement of technical and economic indicators of heat power plants. The practical results of the modernization of irrigation and water distribution system of a cooling tower are presented. As a result, the application of new irrigation and water distribution systems of cooling towers will make it possible to increase the cooling efficiency by more than 4 оС and, therefore, to obtain the fuel savings by improving the vacuum in the turbine condensers. In addition, the available capacity of CHP in the summer period is increased. The results of the work, the experience of modernization of irrigation and water distribution systems of the Gomel CHP-2 cooling towers system, as well as the and methods of calculating of its efficiency can be disseminated for upgrading similar facilities at the power plants of the Belarusian energy system. Some measures are prosed to improve recycling systems, cooling towers and their structures; such measures might significantly improve the reliability and efficiency of technical water supply systems of heat power plants.

Modernization of the automation control system of technological processes at the preparation plant in the conditions of technical re-equipment

Science.gov (United States)

Lyakhovets, M. V.; Wenger, K. G.; Myshlyaev, L. P.; Shipunov, M. V.; Grachev, V. V.; Melkozerov, M. Yu; Fairoshin, Sh A.

2018-05-01

The experience of modernization of the automation control system of technological processes at the preparation plant under the conditions of technical re-equipment of the preparation plant “Barzasskoye Tovarischestvo” LLC (Berezovsky) is considered. The automated process control systems (APCS), the modernization goals and the ways to achieve them are indicated, the main subsystems of the integrated APCS are presented, the enlarged functional and technical structure of the upgraded system is given. The procedure for commissioning an upgraded system is described.

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.

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

Calculation and Designing of Up-to-Date Gas-Flame Plants for Metal Heating and Heat Treatment

Directory of Open Access Journals (Sweden)

V. I. Тimoshpolsky

2008-01-01

Full Text Available An analysis of development trends in the CIS machine-building industry and current status of the heating and heat treatment furnaces of main machine-building enterprises of the Republic of Belarus as of the 1st quarter of 2008 is given in the paper.The paper presents the most efficient engineering solutions from technological and economic point of view that concern calculation and designing of up-to-date gas-flame plants which are to be applied for modernization of the current heating and heat treatment furnaces of the machine-building enterprises in the Republic of Belarus.A thermo-technical calculation of main indices of the up-to-date gas-flame plant has been carried out in the paper.

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.

Technical aspects of coupling a 6300 m3/day MSF-RO desalination plant to a PHWR nuclear power plant

International Nuclear Information System (INIS)

Verma, R.K.

1998-01-01

Presently, eight pressurised Heavy Water Reactors (PHWRs) each of 235 MWe capacity are operational in India. Four more units of similar capacity are expected to be commissioned soon. Work on two units each of 500 MWe capacity is also initiated. Extensive engineering development work has also been carried out in India, both on the MSF process and the membrane process. Based on the experience obtained from the presently operating 425 m 3 /d MSF plant and from the R and D work on the RO process, a 6300 m 3 /d MSF-RO plant (4500 m 3 /d MSF and 1800 m 3 /d RO) has been designed and the work for setting up this plant is undertaken. The steam for the heating duty in the brine heater as well as the steam for the evacuation purpose for the MSF plant is proposed to be obtained from the nuclear plant steam cycle. Sea water feed for the MSF plant as well as for the RO plant will be derived from the sea water discharge system of the nuclear power plant. Provision is made for supply of electrical power also from the power plant. The details of the heating steam supply circuit starting from the steam tapping point on the nuclear plant side to the MSF plant brine heater inlet and the arrangement for the return of condensate to the nuclear plant has been described with component requirement and various technical considerations. All the liquid streams and the steam supplied from the nuclear plant to the desalination plant as well as the product water will be monitored to ensure that there is no radioactive contamination. (author)

CO2 capture from power plants. Part I : A parametric study of the technical performance based on monoethanolamine

NARCIS (Netherlands)

Abu-Zahra, M. R. M.; Schneiders, L. H. J.; Niederer, J. P. M.; Feron, P. H. M.; Versteeg, G. F.

Capture and storage of CO2 from fossil fuel fired power plants is drawing increasing interest as a potential method for the control of greenhouse gas emissions. An optimization and technical parameter study for a CO2 capture process from flue gas of a 600 MWe bituminous coal fired power plant, based

CO2 capture from power plants: Part I. A parametric study of the technical performance based on monoethanolamine

NARCIS (Netherlands)

Abu-Zahra, Mohammad R.M.; Schneiders, Léon H.J.; Niederer, John; Feron, Paul H.M.; Versteeg, Geert

2007-01-01

Capture and storage of CO2 from fossil fuel fired power plants is drawing increasing interest as a potential method for the control of greenhouse gas emissions. An optimization and technical parameter study for a CO2 capture process from flue gas of a 600 MWe bituminous coal fired power plant, based

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

Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

International Nuclear Information System (INIS)

Korsah, K.; Wood, R.T.; Hassan, M.; Tanaka, T.J.

1998-01-01

This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Korsah, K.; Wood, R.T. [Oak Ridge National Lab., TN (United States); Hassan, M. [Brookhaven National Lab., Upton, NY (United States); Tanaka, T.J. [Sandia National Labs., Albuquerque, NM (United States)

1998-01-01

This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants.

The Chernobyl accident and the Spanish nuclear power plants. Technical report

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-11-15

On the morning of April 26, 1986, Unit 4 of the Chernobyl Nuclear Power Plant (Ukraine, USSR) suffered an accident of the greatest magnitude among those which have taken place in nuclear energy installations employed for peaceful uses. The accident reached a degree of severity unknown up to now in nuclear energy generating plants, both with respect to the loss of human lives and the effects caused to the neighboring population (as well as to other nations within a wide radius of radioactivity dispersal), and also with respect to the damage caused in the nuclear plant itself. In the light of the anxiety created internationally, the USSR State Committee for the Utilization of Atomic Energy prepared a report (1), based on the conclusions of the Governmental Commission entrusted to study the causes of the accident, which was presented at the international meeting of experts held at the International Atomic Energy Agency (IAEA) headquarters in Vienna from August 25 to 29, 1986. The present technical report has been prepared by the Spanish nuclear power plants within the framework of UNIDAD ELECTRICA, S.A. (UNESA) - the Association of Spanish electric utilities - in collaboration with EMPRESARIOS AGRUPADOS, S.A. The report reflects the utilities' analyses of the causes and consequences of the accident and, based on similarities and differences with Spanish plants under construction and in operation, intends to: a. Evaluate the possibility of an accident with similar consequences occurring in a Spanish plant b. Identify possible design and operation modifications indicated by the lessons learned from this accident.

The Chernobyl accident and the Spanish nuclear power plants. Technical report

International Nuclear Information System (INIS)

1986-11-01

On the morning of April 26, 1986, Unit 4 of the Chernobyl Nuclear Power Plant (Ukraine, USSR) suffered an accident of the greatest magnitude among those which have taken place in nuclear energy installations employed for peaceful uses. The accident reached a degree of severity unknown up to now in nuclear energy generating plants, both with respect to the loss of human lives and the effects caused to the neighboring population (as well as to other nations within a wide radius of radioactivity dispersal), and also with respect to the damage caused in the nuclear plant itself. In the light of the anxiety created internationally, the USSR State Committee for the Utilization of Atomic Energy prepared a report (1), based on the conclusions of the Governmental Commission entrusted to study the causes of the accident, which was presented at the international meeting of experts held at the International Atomic Energy Agency (IAEA) headquarters in Vienna from August 25 to 29, 1986. The present technical report has been prepared by the Spanish nuclear power plants within the framework of UNIDAD ELECTRICA, S.A. (UNESA) - the Association of Spanish electric utilities - in collaboration with EMPRESARIOS AGRUPADOS, S.A. The report reflects the utilities' analyses of the causes and consequences of the accident and, based on similarities and differences with Spanish plants under construction and in operation, intends to: a. Evaluate the possibility of an accident with similar consequences occurring in a Spanish plant b. Identify possible design and operation modifications indicated by the lessons learned from this accident

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1990-12-01

During the second quarter of 1990 the Finnish nuclear plant units Loviisa 1 and 2 and TVO and II were in commercial operation for most of the time. The feedwater pipe rupture at Loviisa 1 and the resulting inspections and repairs at both Loviisa plant units brought about an outage the overall duration of which was 32 days. The annual maintenance outages of the TVO plant units were arranged during the report period and their combined duration was 31.5 days. Nuclear electricity accounted for 35.3% of the total Finnish electricity production during this quarter. The load factor average of the nuclear power plant units was 83.0%. Three events occurred during the report period which are classified as Level 1 on the International Nuclear Event Scale: feedwater pipe rupture at Loviisa 1, control rod withdrawal at TVO I in a test during an outage when the hydraulic scram system was rendered inoperable and erroneous fuel bundle transfers during control rod drives maintenance at TVO II. Other events during this quarter are classified as Level Zero (Below Scale) on the International Nuclear Event Scale. Occupational radiation doses and external releases of radioactivity were considerably below authorised limits. Only small amounts of nuclides originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1993-12-01

Quarterly reports on the operation of Finnish nuclear power plants describe events and observations related to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Safety-enhancing plant modifications and general matters relating to the use of nuclear energy are also reported. A summary of the radiation safety of plant personnel and the environment, and tabulated data on the plants' production and their load factors are also given. At the Loviisa 1 plant unit one of two specially-backed AC busbars was lost during the second quarter of 1993. A ca. 30 minute voltage break caused malfunctions in the plant unit's electrical equipment and rendered inoperable certain components important to safety. The event is rated on the International Nuclear Event Scale (INES) at level 1. In inspections carried out at TVO II during the annual maintenance outage, the number of cracks detected in control rod structural material was higher than usual. When cracks occur, part of boron carbide, the power regulating medium in control rods, may wash into the reactor water and control rod shutdown capability may be impaired. The event is rated on the INES at level 1. Other events in the second quarter of 1993 had no bearing on nuclear or radiation safety. (4 figs., 5 tabs.)

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1992-03-01

The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost the whole third quarter of 1991. Longer interruptions in electricity generation were caused by the annual maintenances of the Loviisa plant units. The load factor average was 81.7 %. In a test conducted during the annual maintenance outage of Loviisa 1 it was detected that the check valve of the discharge line of one pressurized emergency make-up tank did not open sufficiently at the tank's hydrostatic pressure. In connection with a 1988 modification, a too tightly dimensioned bearing had been mounted on the valve's axle rod and the valve had not been duly tested after the operation. The event is classified as Level 1 on the International Nuclear Event Scale. Other events in this quarter which are classified according to the International Nuclear Event Scale are Level Zero (Below Scale). Occupational radiation doses and releases of radioactive material off-site were below authorised limits in this quarter. Only small amounts of radioactive materials originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

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

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.

Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the James A. Fitzpatrick Nuclear Power Plant (Docket No. 50-333)

International Nuclear Information System (INIS)

Selan, J.C.

1983-01-01

This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the James A. FitzPatrick Nuclear Power Plant. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-01-01

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

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

International Nuclear Information System (INIS)

1996-01-01

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

Technical considerations in repowering a nuclear plant for fossil fueled operation

International Nuclear Information System (INIS)

Patti, F.J.

1996-01-01

Repowering involves replacement of the reactor by a fossil fuel source of steam. This source can be a conventional fossil fueled boiler or the heat recovery steam generator (HRSG) on a gas turbine exhaust. The existing steam turbine plant is used to the extent possible. Alternative fuels for repowering a nuclear plant are coal, natural gas and oil. In today's world oil is not usually an alternative. Selection of coal or natural gas is largely a matter of availability of the fuel near the location of the plant. Both the fossil boiler and the HRSG produce steam at higher pressures and temperatures than the throttle conditions for a saturated steam nuclear turbine. It is necessary to match the steam conditions from the new source to the existing turbine as closely as possible. Technical approaches to achieve a match range from using a topping turbine at the front end of the cycle to attemperation of the throttle steam with feedwater. The electrical output from the repowered plant is usually greater than that of the original nuclear fueled design. This requires consideration of the ability to use the excess electricity. Interfacing of the new facility with the existing turbine plant requires consideration of facility layout and design. Site factors must also be considered, especially for a coal fired boiler, since rail and coal handling facilities must be added to a site for which these were not considered. Additional site factors that require consideration are ash handling and disposal

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

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)

Co-sponsored second quarter progress review conference on district heating

Energy Technology Data Exchange (ETDEWEB)

None

1980-01-01

A summary of the progress review conference on district heating and cooling systems is presented. The agenda and lists of speakers and attendees are presented. A history of district heating and some present needs and future policies are given and an excerpt from the National District Heating Program Strategy (DOE, March 1980) is included. Following the presentation, District Heating and Cooling Systems Program, by Alan M. Rubin, a fact sheet on DOE's Integrated Community Energy Systems Program and information from an oral presentation, District Heating and Cooling Systems for Communities Through Power Plant Retrofit Distribution Network, are given. The Second Quarterly Oral Report to the US DOE on the District Heating and Cooling Project in Detroit; the executive summary of the Piqua, Ohio District Heating and Cooling Demonstration Project; the Second Quarterly Report of the Moorehead, Minnesota District Heating Project; and the report from the Moorehead, Minnesota mayor on the Hot Water District Heating Project are presented.

Coal gasification. Quarterly report, April--June 1977

Energy Technology Data Exchange (ETDEWEB)

None

1978-01-01

The conversion of coal to high-Btu gas requires a chemical and physical transformation of solid coal. However, because coal has widely differing chemical and physical properties, depending on where it is mined, it is difficult to process. Therefore, to develop the most suitable techniques for gasifying coal, ERDA, together with the American Gas Association, is sponsoring the development of several advanced conversion processes. Although the basic coal-gasification chemical reactions are the same for each process, the processes under development have unique characteristics. A number of the processes for converting coal to high Btu and to low Btu gas have reached the pilot plant stage. The responsibility for designing, constructing and operating each of these pilot plants is defined and progress on each during the quarter is described briefly. The accumulation of data for a coal gasification manual and the development of mathematical models of coal gasification processes are reported briefly. (LTN)

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

International Nuclear Information System (INIS)

Kitamura, Masaharu; Yoshikawa, Shinji; Hasegawa, Makoto

1998-03-01

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

Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the Indian Point Nuclear Power Plant, Unit 3 (Docket No. 50-286)

International Nuclear Information System (INIS)

Selan, J.C.

1983-01-01

This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the Indian Point Nuclear Power Plant, Unit 3. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations

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

International Nuclear Information System (INIS)

Kofron, K.L.

1994-01-01

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

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.

Environmental surveillance data report for the first quarter of 1988

International Nuclear Information System (INIS)

Blasing, T.J.; Daniels, K.L.; Goldberg, P.Y.; Horwedel, B.M.; McCollough, I.L.; Osborne-Lee, A.E.; Valentine, C.K.; Wolf, D.A.

1988-08-01

During the first quarter of 1988, over 1800 samples which represent more than 6000 analyses and measurements were collected by the Environmental Monitoring and Compliance (EMC) Department. More than ten real-time monitoring stations, which telemeter 10-minute averaged readings of radiation levels, total precipitation, flows, water, and air quality parameters around ORNL also reported data. In addition, three meteorological towers sent weather data at various heights to a host computer every 15-minutes. Real-time measurements of external gamma radiation are now being reported from several stations, included some recently activated or upgraded stations. Measurements this quarter indicate that external gamma radiation around ORNL is close to background, except at station 4, which is located between the Waste Treatment Plant and waste treatment ponds and therefore experiences higher levels of radiation. Cobalt-60 concentrations in Melton Branch remained low, as they had been during the fourth quarter of 1987. Lack of discharge from the HFIR ponds is the apparent cause of the reduced concentrations, as these ponds appear to be the source of most of the cobalt-60 that does occur in Melton Branch. Flow-weighted concentration of radionuclides in surface water were found to be generally much lower than the DOE derived concentration guidelines except for tritium in Melton Branch. Tritium concentrations measured at Melton Branch Site 1 exceeded the corresponding guideline by 30% during March

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

International Nuclear Information System (INIS)

Chang Oh

2005-01-01

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

Risk management through dynamic technical specifications

International Nuclear Information System (INIS)

Klopp, George T.; Petersen, Thomas A.

2004-01-01

The wide deployment of plant specific probabilistic risk assessments for nuclear power plants has provided the means to effect a fresh risk management perspective and a fresh, risk based, regulatory outlook on nuclear power. There has been a great deal of conversation on risk based regulation within the U. S. nuclear power industry but, curiously, very little on effective risk management. This paper proposes a means to link the two subjects through the plant Technical Specifications. A revised concept for Technical Specifications is suggested which is based on deterministic analyses and probabilistic risk assessments for each plant. The revised Technical Specifications would consider, on a real-time basis, the exact state of the plant in terms of the status of key components and systems. It would depict current plant risk levels and compare those levels to the desired and limiting (alert/action) levels. It would advise the plant operator on the risk impact of proposed actions through a simple query system and illustrate the impact of such actions on plant status relative to designated risk values. The basis for the proposed approach lies in realistic deterministic plant analyses and probabilistic risk assessment (PRA) deployment tools being developed, in parallel, by a number of parties in the U.S. today. These PRAs are based primarily on the existing plant responses to Generic Letter 88-20, 'Individual Plant Examinations' (IPEs). Each of these tools allows the plant operator to input, on a real-time basis, the status of key equipment and systems. The tools then provide explicit illustrations of dependency effects; updated, 'real-time' risk status indications such as core damage frequency; and, in some cases, allow the operator to assess the risk impact of removing from service selected components for maintenance or testing. These systems generally operate on personal computers and provide nearly instantaneous responses to plant queries. Moving from these tools to

Trojan technical specification verification project

International Nuclear Information System (INIS)

Bates, L.; Rickenback, M.

1991-01-01

The Trojan Technical Specification Verification (TTSV) project at the Trojan plant of Portland General Electric Company was motivated by the recognition that many numbers in the Trojan technical specifications (TTS) potentially lacked the consideration of instrument- and/or process-related errors. The plant setpoints were known to consider such errors, but many of the values associated with the limiting conditions for operation (LCO) did not. In addition, the existing plant instrument error analyses were based on industry values that do not reflect the Trojan plant-specific experience. The purpose of this project is to ensure that the Trojan plant setpoint and LCO values include plant-specific instrument error

PSA-based optimization of technical specifications for the Borssele nuclear power plant

International Nuclear Information System (INIS)

Seebregts, A.J.; Schoonakker, H.A.

1996-01-01

The Borssele Nuclear Power Plant (NPP) is a Siemens/KWU 472 MWe Pressurized Water Reactor which has been in operation since 1973. In 1989, a Probabilistic Safety Assessment (PSA) program was initiated to complement deterministic safety studies and operational experience in forming a plant safety concept. In 1993, the PSA-MER model was completed and used to determine the effects a package of proposed modifications would have on plant safety and risks to the environment. This model was used to start retrospective risks profile and allowed outage times (AOTs) analyses, which both concerned the calculation of the change in total core damage frequency (TCDF) given a change in configuration. The main problems identified and reported in this paper are: (i) How to calculate the change in TCDF (ΔTCDF)? (section 3); and (ii) How to set practical decision criteria and how to use the PSA as extension to Technical Specifications (TS) AOTs? (section 4). Finally, a pilot study was conducted in order to optimize surveillance test intervals (STIs) which are also part of the TS (section 5). (orig.)

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.

Resolution of digital instrumentation and control and human factors technical and regulatory issues for new plants and for modernization of operating plants

International Nuclear Information System (INIS)

Naser, J.A.; Torok, R.C.; Canavan, K.T.

2008-01-01

There are several technical and regulatory issues in the areas of digital I and C, human factors, and control rooms needing generic resolution. If they are not generically resolved, they can contribute to protracted regulatory reviews for operating plant license amendments and substantial delays and increased costs for new plant COL approvals. Therefore; a coordinated, proactive program has been established to resolve key issues. Both Industry and NRC have roles in resolving these key issues and addressing them in future design efforts and regulatory reviews. The Industry initiative is led by the NEI Digital I and C and Human Factors Working Group. NRC has established Task Working Groups under the NRC Digital I and C Steering Committee to address the issues and interact with Industry. EPRI is providing technical input and resolution leadership for some of the issues being addressed in three of the task working groups. For the Highly Integrated Control Room - Human Factors Task area, EPRI has taken the lead in developing draft industry position technical reports for the following three issues: 1) Minimum inventory of human system interfaces, 2) Computerized procedures and associated topics of automation and soft controls, and 3) Methodology to determine the acceptability of manual operator actions response times for a BTP 7-19 software common cause failure. For the Diversity and Defense-in-Depth area, EPRI has taken the lead in developing two draft industry position technical papers on the following topics: 1) Integrating defensive measures and diversity attributes to protect against digital common cause failures and 2) Susceptibility of digital devices and components to common cause failures. For the Risk Informing area, EPRI has taken the lead in developing two draft industry position technical papers on the following topics: 1) Clarifying how to use current methods to model digital systems in a PRA and 2) Application of PRA to specific digital I and C issues

Technical Feasibility Study of Thermal Energy Storage Integration into the Conventional Power Plant Cycle

Directory of Open Access Journals (Sweden)

Jacek D. Wojcik

2017-02-01

Full Text Available The current load balance in the grid is managed mainly through peaking fossil-fuelled power plants that respond passively to the load changes. Intermittency, which comes from renewable energy sources, imposes additional requirements for even more flexible and faster responses from conventional power plants. A major challenge is to keep conventional generation running closest to the design condition with higher load factors and to avoid switching off periods if possible. Thermal energy storage (TES integration into the power plant process cycle is considered as a possible solution for this issue. In this article, a technical feasibility study of TES integration into a 375-MW subcritical oil-fired conventional power plant is presented. Retrofitting is considered in order to avoid major changes in the power plant process cycle. The concept is tested based on the complete power plant model implemented in the ProTRAX software environment. Steam and water parameters are assessed for different TES integration scenarios as a function of the plant load level. The best candidate points for heat extraction in the TES charging and discharging processes are evaluated. The results demonstrate that the integration of TES with power plant cycle is feasible and provide a provisional guidance for the design of the TES system that will result in the minimal influence on the power plant cycle.

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

Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Saurwein, John

2011-07-15

This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

International Nuclear Information System (INIS)

Saurwein, J.

2011-01-01

This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

Technical improvement of ATE system of Ling'ao Nuclear Power Plant Phase II

International Nuclear Information System (INIS)

Zhu Xingbao; Xiong Jingchuan; Liang Qiaohong

2009-01-01

In order to solve the problem that the content of SO 4 2- in Steam Generator significantly increased beyond the criteria after the use of the condensate treatment (ATE) system in Daya Bay Nuclear Power Plant and Ling'ao Nuclear Power Plant Phase I, technical improvement have been conducted on the sizes of the fore cation bed and the mixed bed, water distributing devices, ion exchange resins and separation facility. The effectiveness for the ion exchange of the mixed bed is improved, the resolved substance of cation resin is decreased; it is more impossible for fragments and powder which would lead high SO 4 2- content in Steam Generator. Finally, the quality of the steam-water could be improved and ensured. (authors)

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.

Technologies for improving the availability and reliability of current and future water cooled nuclear power plants. Proceedings of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-11-01

One of the activities of the IAEA is to provide all Member States with an international source of balanced, objective information on advanced in technology for water cooled reactors. Since the global nuclear industry has a common interest in improving plant availability and reliability to assure specific individual plant and country perspective as well as to have an image of well managed competitive industry, the IAEA held a Technical Committee Meeting on Technologies for Improving the Availability and Reliability of Current and Future Water Cooled Nuclear Power Plants in September 1997. The basic aim to was to identify, review and exchange information on international developments in technologies for achieving high availability and reliability and to suggest areas where further technical advances could contribute to improvement of performance. Designs for future plants were presented in the context of how they can accommodate both the organizational and technical means for reaching even higher levels of performance. This proceedings contains the contributed papers presented at this Meeting each with a separate abstract. Four sessions were concerned with: policies, practices and procedures for achieving high reliability and availability; improving availability and reliability through better use of today`s technologies; recent advances in technologies for improving availability and reliability; achieving high availability for new plants Refs, figs, tabs

Technologies for improving the availability and reliability of current and future water cooled nuclear power plants. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1998-11-01

One of the activities of the IAEA is to provide all Member States with an international source of balanced, objective information on advanced in technology for water cooled reactors. Since the global nuclear industry has a common interest in improving plant availability and reliability to assure specific individual plant and country perspective as well as to have an image of well managed competitive industry, the IAEA held a Technical Committee Meeting on Technologies for Improving the Availability and Reliability of Current and Future Water Cooled Nuclear Power Plants in September 1997. The basic aim to was to identify, review and exchange information on international developments in technologies for achieving high availability and reliability and to suggest areas where further technical advances could contribute to improvement of performance. Designs for future plants were presented in the context of how they can accommodate both the organizational and technical means for reaching even higher levels of performance. This proceedings contains the contributed papers presented at this Meeting each with a separate abstract. Four sessions were concerned with: policies, practices and procedures for achieving high reliability and availability; improving availability and reliability through better use of today's technologies; recent advances in technologies for improving availability and reliability; achieving high availability for new plants

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....

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.

Ageing management technical information investigations

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

In February 2013, there are 50 units of commercial nuclear power plants (NPPs) in Japan. We enter into a period that 20 units of them are operating for more than 30 years. Currently, regulation imposes utilities to conduct ageing technical evaluations of each unit before operation of 30 years from the commissioning, to develop the long term maintenance management policy for next 10 years and to submit to the regulatory authority the policy with the report on ageing management technical evaluation (AMTE) for each NPP. It is necessary for regulatory side to develop technical information bases incorporating latest technical knowledge as operating experiences in domestic and abroad on ageing of the plants necessary to conduct reviews of AMTE for each unit. Based on these standpoints, technical information bases investigations have been conducted from the viewpoints of material degradation of ageing NPPs. In order to develop scientific regulator judgment bases related to ageing management (AM) and long-term operation (LTO), investigations on latest information on ageing management in domestic and abroad are conducted and a set of documents including technical evaluation review manuals necessary to conduct AMTE are prepared. To utilize the results of the investigations for ageing technical evaluation, database including latest information related to AM and LTO are developed, ran and operated. In addition, investigations related to Fugen nuclear plant, under decommissioning plants, investigations on mechanism of stress corrosion cracking (SCC), thermal ageing and preventive technologies for SCC, detection and diagnosis technology for ageing degradation and condition monitoring technology are performed to validate and confirm effectiveness of the technologies. (author)

Development of Molten-Salt Heat Transfer Fluid Technology for Parabolic Trough Solar Power Plants - Public Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Grogan, Dylan C. P.

2013-08-15

Executive Summary This Final Report for the "Development of Molten-Salt Heat Transfer Fluid (HTF) Technology for Parabolic Trough Solar Power Plants” describes the overall project accomplishments, results and conclusions. Phase 1 analyzed the feasibility, cost and performance of a parabolic trough solar power plant with a molten salt heat transfer fluid (HTF); researched and/or developed feasible component options, detailed cost estimates and workable operating procedures; and developed hourly performance models. As a result, a molten salt plant with 6 hours of storage was shown to reduce Thermal Energy Storage (TES) cost by 43.2%, solar field cost by 14.8%, and levelized cost of energy (LCOE) by 9.8% - 14.5% relative to a similar state-of-the-art baseline plant. The LCOE savings range met the project’s Go/No Go criteria of 10% LCOE reduction. Another primary focus of Phase 1 and 2 was risk mitigation. The large risk areas associated with a molten salt parabolic trough plant were addressed in both Phases, such as; HTF freeze prevention and recovery, collector components and piping connections, and complex component interactions. Phase 2 analyzed in more detail the technical and economic feasibility of a 140 MWe,gross molten-salt CSP plant with 6 hours of TES. Phase 2 accomplishments included developing technical solutions to the above mentioned risk areas, such as freeze protection/recovery, corrosion effects of applicable molten salts, collector design improvements for molten salt, and developing plant operating strategies for maximized plant performance and freeze risk mitigation. Phase 2 accomplishments also included developing and thoroughly analyzing a molten salt, Parabolic Trough power plant performance model, in order to achieve the project cost and performance targets. The plant performance model and an extensive basic Engineering, Procurement, and Construction (EPC) quote were used to calculate a real levelized cost of energy (LCOE) of 11.50�

Floating nuclear energy plants for seawater desalination. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1997-05-01

Floating nuclear desalination facilities are one of the alternatives being considered. They may offer a particularly suitable choice for remote locations and small island or coastal communities where the necessary manpower and infrastructure to support desalination plants are not available. In the interest of focusing specific attention on the technology of floating nuclear desalination, the IAEA sponsored a Technical Committee Meeting on Floating Nuclear Plants for Seawater Desalination from 29 to 31 May 1995 in Obninsk, Russian Federation. This publication documents the papers and presentations given by experts from several countries at that meeting. It is hoped that the information contained in this report will be a valuable resource for those interested in nuclear desalination, and that it will stimulate further interest in the potential for floating nuclear desalination facilities. Refs, figs, tabs

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

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

Science.gov (United States)

Selwitz, Jason Lawrence

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

Application of data-processing to the technical and economical management of the plants of Simo

International Nuclear Information System (INIS)

Chastagner, F.

1988-01-01

The firm Simo is entrusted with the processing of the uranium ores extracted from the mines of Cogema in France, in its three plants. The paper describes the conception and the functioning of the information system. Among the advantages contributed by the system, the coherence between the technical follow-up and the economical follow-up constitutes one of the principal progressive features [fr

technical guidelines for the design and construction of the next generation of nuclear power plants with pressurized water reactors

International Nuclear Information System (INIS)

2009-01-01

These technical guidelines present the opinion of the French 'Groupe Permanent charge des Reacteurs nucleaires' (GPR) concerning the safety philosophy and approach as well as the general safety requirements to be applied for the design and construction of the next generation of nuclear power plants of the PWR (pressurized water reactor) type, assuming the construction of the first units of this generation would start at the beginning of the 21. century. These technical guidelines are based on common work of the French Institut de Protection et de Surete Nucleaire (IPSN) and of the German Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS). Moreover, these technical guidelines were extensively discussed with members of the German Reaktor Sicherheitskommission (RSK) until the end of 1998 and further with German experts. The context of these technical guidelines must be clearly understood. Faced with the current situation of nuclear energy in the world, the various nuclear steam supply system designers are developing new products, all of them claiming their intention of obtaining a higher safety level, by various ways. GPR believes that, for the operation of a new series of nuclear power plants at the beginning of the next century, the adequate way is to derive the design of these plants in an 'evolutionary' way from the design of existing plants, taking into account the operating experience and the in-depth studies conducted for such plants. Nevertheless, introduction of innovative features must also be considered in the frame of the design of the new generation of plants, especially in preventing and mitigating severe accidents. GPR underlines here that a significant improvement of the safety of the next generation of nuclear power plants at the design stage is necessary, compared to existing plants. If the search for improvement is a permanent concern in the field of safety, the necessity of a significant step at the design stage clearly derives from better

Technical and economic assessment of the integrated solar combined cycle power plants in Iran

International Nuclear Information System (INIS)

Soltani Hosseini, M.; Hosseini, R.; Valizadeh, G.H.

2002-01-01

Thermal efficiency, capacity factor, environmental considerations, investment cost, fuel and O and M costs are the main parameters for technical and economic assessment of solar power plants. This analysis has shown that the Integrated Solar Combined Cycle System with 67 MW e solar field(ISCCS-67) is the most suitable plan for the first solar power plant in Iran. The Levelized Energy Costs of combined cycle and ISCCS-67 power plants would be equal if 49 million dollars of ISCCS-67 capital cost supplied by the international environmental organizations such as Global Environmental Facilities and World Bank. This study shows that an ISCCS-67 saves 59 million dollars in fuel consumption and reduces about 2.4 million ton in CO 2 emission during 30 years operating period. Increasing of steam turbine capacity by 50%, and 4% improvement in overall efficiency are other advantages of iSCCS-67 power plant. The LEC of ISCCS-67 is 10% and so 33% lower than the combined cycle and gas turbine, respectively, at the same capacity factor with consideration of environmental costs

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...

Mixed Waste Management Facility groundwater monitoring report: Third quarter 1994

International Nuclear Information System (INIS)

1994-12-01

Currently, 125 wells monitor groundwater quality in the uppermost aquifer beneath the Mixed Waste Management Facility (MWMF) at the Savannah River Site. Samples from the wells are analyzed for selected heavy metals, herbicides/pesticides, indicator parameters, radionuclides, volatile organic compounds, and other constituents. As in previous quarters, tritium and trichloroethylene were the most widespread elevated constituents during third quarter 1994. Sixty-four (51%) of the 125 monitoring wells contained elevated tritium activities. Trichloroethylene concentrations exceeded the final PDWS in 22 (18%) wells. Chloroethene, 1,1-dichloroethylene, and tetrachloroethylene, elevated in one or more wells during third quarter 1994, also occurred in elevated levels during second quarter 1994. These constituents generally were elevated in the same wells during both quarters. Gross alpha, which was elevated in only one well during second quarter 1994, was elevated again during third quarter. Mercury, which was elevated during first quarter 1994, was elevated again in one well. Dichloromethane was elevated in two wells for the first time in several quarters

PUREX Plant aggregate area management study technical baseline report

International Nuclear Information System (INIS)

DeFord, D.H.; Carpenter, R.W.

1995-05-01

The PUREX aggregate area is made up of six operable units; 200-PO-1 through 200-PO-6 and consists of liquid and solid waste disposal sites in the vicinity of, and related to, PUREX Plant operations. This report describes PUREX and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches and ditches, ponds, catch tanks, settling tanks, diversion boxes, underground tank farms, and the lines and encasements that connect them. Each waste site in the aggregate area is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. This document provides a technical baseline of the aggregate area and results from an environmental investigation. This document is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted

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.)

Cycling of conventional power plants: Technical limits and actual costs

International Nuclear Information System (INIS)

Van den Bergh, Kenneth; Delarue, Erik

2015-01-01

Highlights: • Literature reports a wide range of cycling parameters (technical and cost-related). • The impact of different cycling parameters is assessed. • The German 2013 system is studied as a case study. • Even for stringent parameters, the dynamic limit of the portfolio is not reached. • Cycling costs can be reduced with 40% when taken into account in the scheduling. - Abstract: Cycling of conventional generation units is an important source of operational flexibility in the electricity generation system. Cycling is changing the power output of conventional units by means of ramping and switching (starting up and shutting down). In the literature, a wide range of technical and cost-related cycling parameters can be found. Different studies allocate different cycling parameters to similar generation units. This paper assesses the impact of different cycling parameters allocated to a conventional generation portfolio. Both the technical limitations of power plants and all costs related to cycling are considered. The results presented in this paper follow from a unit commitment model, used for a case study based on the German 2013 system. The conventional generation portfolio has to deliver different residual load time series, corresponding to different levels of renewables penetration. The study shows, under the assumptions made, that although the dynamic limits of some units are reached, the limits of the conventional generation portfolio as a whole are not reached, even if stringent dynamic parameters are assigned to the generation portfolio and a highly variable residual load is imposed to the system. The study shows also the importance of including full cycling costs in the unit commitment scheduling. The cycling cost can be reduced by up to 40% when fully taken into account

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)

Organizational factors influencing human performance in nuclear power plants. Report of a technical committee meeting

International Nuclear Information System (INIS)

1997-05-01

In 1991 a Safety Series report on Safety Culture of the International Nuclear Safety Advisory Group (INSAG) was published as 75-INSAG-4 by the IAEA. This report deals with the concept of Safety Culture as it relates to organizations and individuals involved in the operations of nuclear power plants (NPPs). Generally, the role of management and organization in assuring the safe operation of NPPs has been widely recognized and its importance accepted. However, the understanding of what constitutes effective management and organization the area of safety is less developed than the understanding of most of the technical issues which plant operators and regulatory bodies are confronted with. The Technical Committee meeting provided a forum for a broad exchange of information on practices and experiences in the area of organization and management to accomplish operational safety in NPPs and thus enhance Safety Culture. This report and the papers presented at the meeting discuss those factors which influence and improve human performance covering both aspects, i.e. the basic requirements imposed on the operator and the ways of managerial support which enhance the reliable and safety oriented performance of operators. Refs, figs, tabs

Nuclear power plant diagnostics - Safety aspects and licensing. Report of a technical committee meeting. Working material

International Nuclear Information System (INIS)

1997-01-01

The aim of the Technical Committee Meeting (TCM) was to review developed systems and methods in diagnostics in the scope of their impacts and importance to the safety of Nuclear Power Plants. Papers presented on TCM came from different sources, from developers, from manufacturers, from licensing authorities and from NPP personal. They reflect up to date status in the given subject. Participants of TCM formulated three working groups to elaborate different questions which were raised during the discussions. Their results are reflected in the three chapter titles of the given material. Annex 1 to this document contains presentations made at the Technical Committee Meeting. Refs, figs, tabs

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.

Technical, economic and environmental potential of co-firing of biomass in coal and natural gas fired power plants in the Netherlands

International Nuclear Information System (INIS)

Van Ree, R.; Korbee, R.; Eenkhoorn, S.; De Lange, T.; Groenendaal, B.

2000-01-01

In this paper the technical, economic, and environmental potential of co-firing of biomass in existing Dutch coal and natural gas fired power plants, and industrial combined-cycles (CC), is addressed. Main criteria that are considered are: the availability and contractibility of biomass for energy purposes; the (technical) operation of the conventional fossil fuel based processes may not be disturbed; the gaseous and liquid plant emissions have to comply to those applicable for power plants/CCs, the commercial applicability of the solid residues may not be negatively influenced; applicable additional biomass conversion technologies must be commercially available; the necessary additional investment costs must be acceptable from an economic point of view, and the co-firing option must result in a substantial CO 2 -emission reduction. The main result of the study described in the paper is the presentation of a clear and founded indication of the total co-firing potential of biomass in existing power plants and industrial CCs in the Netherlands. This potential is determined by considering both technical, economic, and environmental criteria. In spite of the fact that the co-firing potential for the specific Dutch situation is presented, the results of the criteria considered are more generally applicable, and therefore are also very interesting for potential co-firing initiatives outside of the Netherlands

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.

Technical specifications, Callaway Plant, Unit No. 1. Appendix A to license No. NPF-25 (Docket No. STN 50-483)

International Nuclear Information System (INIS)

Anderson, F.D.

1984-06-01

Technical specifications are presented for the limiting conditions for operation and surveillance requirements for the reactor core, reactivity control systems, power distribution limits, instrumentation, reactor coolant system, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations, special test exceptions, radioactive effluents, radiological environmental monitoring; design features of the site, containment, core, coolant system, and fuel storage; and plant staff organization

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

Weldon Spring Site Remedial Action Project Federal Facilities Agreement: Quarterly environmental data summary for third quarter 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-11-06

In support of the Weldon Spring Site Remedial Action Project Federal Facilities Agreement, a copy of the Quarterly Environmental Data Summary (QEDS) for the third quarter of 1998 is enclosed. The data presented in this letter and attachment constitute the QEDS. 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 third quarter of 1998. Air monitoring data presented are the most recent complete sets of quarterly data. 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 the event that above normal data occur.

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 update on pressure suppression type containments in use in U.S. light water reactor nuclear power plants

International Nuclear Information System (INIS)

1978-07-01

In 1972, Dr. S. H. Hanauer (Technical Advisor to the NRC's Executive Director for Operations) wrote a memorandum that raised several questions on the viability of pressure suppression containment concepts. The concerns raised by Dr. Hanauer have recently become the subject of considerable discussion by several members of the U.S. Congress and public. The report provides a response to these expressed concerns and a status summary for various technical matters that relate to the safety of pressure suppression type containments for light water cooled reactor plants

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.

Improving the action requirements of technical specifications: A risk-comparison of continued operation and plant shutdown

International Nuclear Information System (INIS)

Kim, I.S.; Samanta, P.K.

1994-01-01

When the systems needed to remove decay heat are inoperable or degraded, the risk of shutting down the plant may be comparable to, or even higher than, that of continuing power operation with the equipment inoperable while giving priority to repairs. This concern arises because the plant may not have sufficient capability for removing decay heat during the shutdown. However, Technical Specifications (TSs) often require ''immediate'' shutdown of the plant. In this paper, the authors present risk-based analyses of the various operational policy alternatives available in such situations, with an example application to the standby service water (SSW) system of a BWR. These analyses can be used to define risk-effective requirements for those standby safety systems under discussion

Improving the action requirements of technical specifications: A risk-comparison of continued operation and plant shutdown

Energy Technology Data Exchange (ETDEWEB)

Kim, I.S.; Samanta, P.K. [Brookhaven National Lab., Upton, NY (United States); Mankamo, T.

1995-04-01

When the systems needed to remove decay heat are inoperable or degraded, the risk of shutting down the plant may be comparable to, or even higher than, that of continuing power operation with the equipment inoperable while giving priority to repairs. This concern arises because the plant may not have sufficient capability for removing decay heat during the shutdown. However, Technical Specifications (TSs) often require {open_quotes}immediate{close_quotes} shutdown of the plant. In this paper, we present risk-based analyses of the various operational policy alternatives available in such situations, with an example application to the standby service water (SSW) system of a BWR. These analyses can be used to define risk-effective requirements for those standby safety systems under discussion.

Guideline for the seismic technical evaluation of replacement items for nuclear power plants

International Nuclear Information System (INIS)

Harris, S.P.; Cushing, R.W.; Johnson, H.W.; Abeles, J.M.

1993-02-01

Seismic qualification for equipment originally installed in nuclear power plants was typically performed by the original equipment suppliers or manufactures (OES/OEM). Many of the OES/OEM no longer maintain quality assurance programs with adequate controls for supplying nuclear equipment. Utilities themselves must provide reasonable assurance in the continued seismic adequacy of such replacement items. This guideline provides practical, cost-effective techniques which can be used to provide reasonable assurance that replacement items will meet seismic performance requirements necessary to maintain the seismic design basis of commercial nuclear power plants. It also provides a method for determining when a seismic technical evaluation of replacement items (STERI) is required as part of the procurement process for spare and replacement items. Guidance on supplier program requirements necessary to maintain continued seismic adequacy and on documentation of maintaining required seismic adequacy is also included

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.

Using plant status data for off-site emergency management: Technical and political aspects

International Nuclear Information System (INIS)

Govaerts, P.

2004-01-01

Subsequent to the TMI and Chernobyl accidents, emergency management is investigating the possibility of taking balanced decisions on interventions as early as possible. This process relies more and more on in-plant data to assess the term of releases. The paper discusses the regulatory aspects of the communication related to the source term between the utility and the national authorities, and the authorities of a host country and neighbouring countries that may be affected. The technical aspects of the assessment process are summarised, with the emphasis on the handling of uncertainties. Notwithstanding the technical progress, the main dilemma for the decision makers remains the same. Risk management and prevention measures become more familiar to authorities. Utilities and national authorities have to get rid of complexes with respect to accidents covered by the accepted residual risk. International emergency management has to look for an organisation type ensuring the continuity of countermeasures independent of the presence of administrative borders, and with respect to national autonomies. (authors)

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1994-06-01

Quarterly reports on the operation of the Finnish NPPs describe nuclear and radiation safety related events and observations which the Finnish Centre for Radiation and Nuclear Safety considers significant. Safety improvements at the plants and general matters relating to the use of nuclear energy are also reported. A summary of the radiation safety of plant personnel and the environment, and tabulated data on the plants' production and load factors are also given. One event during the last quarter of 1993 was rated on the International Nuclear Event Scale (INES) as level 1. During this event at Loviisa 2, the secondary circuit emergency feedwater system was erroneously isolated from automatic start-up readiness. The error went unnoticed for 4.5 hours. During 1993 one level 2 incident and three level 1 incidents occurred at the Finnish NPPs. (8 figs., 4 tabs.)

The Apatity nuclear heating plant project: modern technical and economic issues of nuclear heat application in Russia

International Nuclear Information System (INIS)

Adamov, E.O.; Romenkov, A.A.

1998-01-01

Traditionally Russia is a country with advanced structure of centralized heat supply. Many thermal plants and heating networks need technical upgrading to improve their technical and economic efficiency. Fossil fuelled heating capacities have a negative influence on ecology, which can be seen especially in the northern regions of Russia. Furthermore, fossil fuel prices are rising in Russia. The above factors tend to intensify the need for alternative heat sources being capable of solving the problem. Nuclear heat sources may be the alternative. In this paper, the main features of a proposed NHP in the Murmansk region are summarized. (author)

Palisades technical specification conversion from custom to new industry standard

International Nuclear Information System (INIS)

Foley, D.J.; Young, B.

1990-01-01

Consumers Power Company's (CPCo) Palisades plant is in the process of converting from custom technical specifications to the new industry standard, Restructured Standard Technical Specifications (RSTS). Custom technical specifications were the precursor to standard technical specifications, being issued to plants built prior to 1972. In May 1989, each of the four light water reactor owners' groups completed topical reports presenting their version of Restructured Standard Technical Specifications to the Nuclear Regulatory Commission (NRC). After approval of the owners' groups versions of the RSTs by the NRC, individual operating reactors will begin to make the conversion to the RSTS. Each owners' group has designated a lead plant, which will be the first of that vendor type to convert. All of the lead plants currently operate under standard technical specifications. The content of the RSTS was determined by comparing the standard technical specifications with selection criteria specified in the Commissions Interim Policy Statement

EARLY ENTRANCE CO-PRODUCTION PLANT--DECENTRALIZED GASIFICATION COGENERATION TRANSPORTATION FUELS AND STEAM FROM AVAILABLE FEEDSTOCKS

Energy Technology Data Exchange (ETDEWEB)

John W. Rich

2001-03-01

Waste Processors Management, Inc. (WMPI), along with its subcontractors Texaco Power and Gasification (now ChevronTexaco), SASOL Technology Ltd., and Nexant Inc. entered into a Cooperative Agreement with the USDOE, National Energy Technology Laboratory (NETL) to assess the techno-economic viability of building an Early Entrance Co-Production Plant (EECP) in the US to produce ultra clean Fischer-Tropsch (FT) transportation fuels with either power or steam as the major co--product. The EECP design includes recovery and gasification of low-cost coal waste (culm) from physical coal cleaning operations and will assess blends of the culm with coal or petroleum coke. The project has three phases: Phase 1 is the concept definition and engineering feasibility study to identify areas of technical, environmental and financial risk. Phase 2 is an experimental testing program designed to validate the coal waste mixture gasification performance. Phase 3 updates the original EECP design based on results from Phase 2, to prepare a preliminary engineering design package and financial plan for obtaining private funding to build a 5,000 barrel per day (BPD) coal gasification/liquefaction plant next to an existing co-generation plant in Gilberton, Schuylkill County, Pennsylvania. The current report is WMPI's third quarterly technical progress report. It covers the period performance from October 1, 2001 through December 31, 2001.

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.

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....

Compliance with technical codes becomes obligatory for receipt of feed-in tariff and ancillary services bonus for wind power plants in Germany

Energy Technology Data Exchange (ETDEWEB)

Boemer, Jens. C. [Ecofys Germany GmbH, Berlin (Germany). Power Systems and Markets Group; Delft Univ. of Technology (Netherlands). Electrical Power Systems Group; Burges, Karsten [Ecofys Germany GmbH, Berlin (Germany). Power Systems and Markets Group; Kumm, Thomas [VDE, Network Technology and Operation Forum (FNN), Berlin (Germany); Poeller, Markus [DIgSILENT GmbH, Gomaringen (Germany)

2009-07-01

The German government aims at a share of electricity generation based on renewable sources (RES-E) of more than 30% by 2020. A major part of this share will be reached by the use of wind power plants (WPP). Therefore, when amending the Renewable Energy Sources Act (EEG) in June 2008, the German government acknowledged the importance of enhanced technical requirements for WPP and announced the development of a respective technical ordinance. For all WPP that go into operation after June 2010, full grid code-compliance becomes a precondition for privileged network access, receipt of feed-in tariff, and extra payments (''ancillary services bonus''). The basis for the technical requirements in the EEG has been laid down by Medium-Voltage (MV)-Directive 2008 and the TransmissionCode 2007. However, the work of the authors - consulting the German government during the development of the technical ordinance - showed that the TransmissionCode 2007 needed careful review and some clarifying specifications were proposed. Eventually, the so called ''Ancillary Services Ordinance'' for wind power plants went into power in July 2009. The interrelation between all three grid codes as well as their specifications and implications for renewable energy sources generators, with special regard to wind power plants, are presented in this paper. (orig.)

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.

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1990-08-01

During the first quarter of 1990 the Finnish nuclear power plant units Loviisa 1 and 2 and TVO I and II were in commercial operation for most of the time. Nuclear electricity accounted for 32.5% of the total Finnish electricity production during this quarter. The load factor average of the nuclear power plant units was 99.0%. An international nuclear event scale has been introduced for the classification of nuclear power plant events according to their nuclear and radiation safety significance. The scale first undergoes about a year long trial period in several countries. on the scale, events are divided into levels from 1 to 7 of which events at Level 7 are the most serious. Furthermore, Level 0 (Below Scale) is used for events with no safety significance. All events which occurred at the Finnish nuclear power plants this quarter are classified as Level 0. Occupational radiation doses and external releases of radioactivity were considerably below authorised limits. At the Loviisa plant, a back-up emergency feedwater system independent of the plant's other systems has been introduced which offers a new, alternative means of removing residual heat from the reactor. Owing to this system, the risk of a severe accident has been further reduced. At the TVO plants, systems have been introduced by which accident sequences which lead to containment failure could be eliminated and the consequences of a potential severe accident could be mitigated. In this report, also the release of short-lived radioactive materials along the transfer route of an irradiated sample is described which occured at the FiR 1 research reactor. The amounts of radioactive materials individuals received in their bodies in connection with this event were very low

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.

Scientific-technical cooperation with foreign (esp. Europe and INSC partner countries) nuclear regulatory authorities and their technical support organizations in the fields of nuclear safety of operating nuclear power plants and on the concept evaluation of generation 3+ plants. Final report

International Nuclear Information System (INIS)

Wolff, Holger

2016-09-01

The BMUB/BfS-Project 3614I01512 forms the frame of the GRS for the scientific-technical cooperation with Technical Support Organisations and Nuclear Regulatory Authorities in the field of nuclear safety in operating NPPs and for the concept evaluation of generation 3 + plants in Europe and INSC Partner Countries. In the present final project report results are described which were gained within the project duration 15.10.2014 up to the 30.09.2016 in the following working packages: Investigations following the catastrophe of Fukushima Daiichi, Evaluation of selected National Action Plans, DBA and severe accident analyses for NPP with PWR (WWER-440, WWER-1000), cooperation with INSC partner countries on DBA, BDBA and severe accident analyses for WWER plants of generation 3 + and building NRA and safety evaluation capacities and decommissioning of nuclear facilities and disposal of radioactive waste. The results are preceded by an outline on the activities related to the project management and to the planning of the bilateral work.

Engaging Local Stakeholders on Technical Issues: Test Case at the La Hague Reprocessing Plant - 59211

International Nuclear Information System (INIS)

Gilli, Ludivine

2012-01-01

In 2009 and 2010, the Institute for Nuclear Safety and Radiation Protection (IRSN) lead a pilot action dealing with the decommissioning of a workshop located on the site of Areva's La Hague fuel-reprocessing plant site in Northwestern France. The purpose of the pilot program was to test ways for IRSN and a few local stakeholders (Non-Governmental Organizations (NGOs) members, local elected officials, etc.) to engage in technical discussions. The discussions were intended to enable the local stakeholders to review the operator's decommissioning application and provide input. The pilot program confirmed there is a definite challenge in successfully opening a meaningful dialogue to discuss technical issues. Three factors influence the extent of the challenge: the knowledge gap between experts and local stakeholders, the conflict between transparency and confidentiality which is inherent with technical topics, and the difficulty for an official expertise institute to hold a dialogue with 'outsiders' during an ongoing reviewing process in which it is participating. The pilot program, given its mixed results, also provided valuable lessons for further improvement of stakeholders' involvement. (authors)

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...

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

International Nuclear Information System (INIS)

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

1984-01-01

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

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1993-06-01

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 considers significant. Also other events of general interest are reported. The reports also include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the plants' production and load factors

Nuclear power plant shift technical advisor. Recommendations for position description, qualifications, education and training

International Nuclear Information System (INIS)

1981-01-01

The purpose of this document is to describe the position and identify specific areas of formal education, plant-specific training and experience necessary to assure an advanced level of analytical ability on shift. These recommendations will provide a level of technical ability that is essential to improved operational safety and are consistent with regulatory requirements. This position was developed in conjunction with representatives of utilities, equipment vendors and engineering educators, giving consideration to specific contributions the function must make to shift operations

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

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.)

Technical specification optimization program - engineered safety features

International Nuclear Information System (INIS)

Andre, G.R.; Jansen, R.L.

1986-01-01

The Westinghouse Technical Specification Program (TOP) was designed to evaluate on a quantitative basis revisions to Nuclear Power Plant Technical Specifications. The revisions are directed at simplifying plant operation, and reducing unnecessary transients, shutdowns, and manpower requirements. In conjunction with the Westinghouse Owners Group, Westinghouse initiated a program to develop a methodology to justify Technical Specification revisions; particularly revisions related to testing and maintenance requirements on plant operation for instrumentation systems. The methodology was originally developed and applied to the reactor trip features of the reactor protection system (RPS). The current study further refined the methodology and applied it to the engineered safety features of the RPS

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...

STEPS: source term estimation based on plant status phase 0 - the technical specifications of the containment module

International Nuclear Information System (INIS)

Vamanu, D.V.

1998-01-01

In the framework of Project RODOS (Real-Time On-Line Decision Support System for Nuclear Emergencies in Europe), the European Atomic Energy Community (EAEC) of the Commission of the European Communities has commissioned the development of a unified concept, body of knowledge, models and software package meant to assist the evaluation of the source term of severe nuclear accidents in light water reactors of the types prevailing on the Continent. Code-named STEPS, for 'Source Term Estimation based on Plant Status', the project has evolved as Contract RODOS D (FI4P-CT96-0048), between EAEC and consortium of expert European centres including Commissariat a l'Energie Atomique, Institut de Protection et de Surete Nucleaire, (CEA-DPI-SEAC) as Coordinator and Forschungszentrum Karlsruhe GmbH (FZK-INR), the Finnish Centre for Radiation and Nuclear Safety, (STUK-NSD), the Technical Research Centre of Finland, Energy, Nuclear Energy (VTT-ET-NE), and Eidgenossische Technische Hochschule - ETH Zurich, Centre of Excellence (ETH-CERS) as Contractors. For the Phase 0 of the project, an IFIN-HH expert has been assigned by ETH-CERS to develop the Technical Specifications of the delivery component of the intended STEPS package, the CONTAINMENT Module. Sponsored by ETH-CERS headquarters in Zurich, the work was done on the premises and with the logistic support of CEA D PI-SEAC at Fontenay-aux-Roses, with the feedback processing and computer code development subsequently performed in Bucharest. The Technical Specifications of the STEPS CONTAINMENT Module were guided by specific terms of reference, including: (i) the capability of the software to function as a source term interface between targeted nuclear power plants and the RODOS System; (ii) the comparable capability of the system to be operated as a stand-alone assessment and decision support tool for a comprehensive variety of plants, nuclear emergency classes. On the technical side, the specifications had to focus on the possible

Proposed design modifications and technical specification changes on grid voltage degradation for the Point Beach Nuclear Plant, Units 1 and 2 (Docket Nos. 50-266 and 50-301). Technical evaluation report

International Nuclear Information System (INIS)

White, R.L.

1981-01-01

This report documents the technical evaluation of the proposed design mofifications and Technical Specification changes for protection of Class 1E equipment from grid voltage degradation for the Point Beach Nuclear Plant, Units 1 and 2. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation compares the submittals made by the licensee with the NRC staff positions and the review criteria and presents the reviewer's conclusion on the acceptability of the proposed system

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.

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