Energy Technology Data Exchange (ETDEWEB)
This report describes a comparison result of technical standards applied to instrumentation and control systems for nuclear power plants between in Korea and in Russia. Russia also has a state-run organization authorized to conduct approval, cancellation, and audit in use of nuclear facility or equipment. The Russian standards for nuclear instrumentation and control equipment are analogous with the Korean ones in the aspect of basic concepts and principles. However, there are some differences in document structure, design requirements, qualification test items, depth of contents between two standard systems. The biggest deviation exists in the standard documents for seismic qualification and electromagnetic interference qualification. Korean seismic qualification standard utilizing US approach, defines testing and qualification methods specifically and clearly. ...
2005-04-15
This report assesses the water quality related benefits that would be expected if the US Environmental Protection Agency (EPA) adopts the proposed effluent limitations, guidelines and pretreatment standards for the Centralized Waste Treatment (CWT) Industry. EPA estimates that under baseline conditions 205 CWT facilities discharge approximately 5.22 million lbs/year of metal and organic pollutants.
1998-12-01
Quality assurance requirements for the design of nuclear fuel reprocessing facilities
International Nuclear Information System (INIS)
Requirements and guidance are provided for a quality assurance program for the design of nuclear fuel reprocessing facilities involving structures, systems and components whose satisfactory performance is required to prevent accidents that could cause undue risk to the health and safety of the public, or to mitigate the consequences of such accidents if they were to occur. The standard is to be used in conjunction with ANSI N46.2.
High level waste storage tanks 242-A evaporator S/RID phase II assessment report
Energy Technology Data Exchange (ETDEWEB)
This document, the Standards/Requirements Identification Document (S/RID) Phase 2 Assessment Report for the subject facility, represents the results of a Performance Assessment to determine whether procedures containing S/RID requirements are fully implemented by field personnel in the field. It contains a summary report and three attachments; an assessment schedule, performance objectives, and assessments for selected functional areas.
1996-09-27
Development of a Standard Data Base and Computer ...
... (Author). Descriptors : (*TERMINAL FLIGHT FACILITIES ... PROGRAMMING, HANDLING), QUEUEING THEORY, STOCHASTIC PROCESSES ...
1973-01-01
FFTF (Fast Flux Test Facility) Reactor Characterization Program: Absolute Fission-rate Measurements
Energy Technology Data Exchange (ETDEWEB)
Absolute fission rate measurements using modified National Bureau of Standards fission chambers were performed in the Fast Flux Test Facility at two core locations for isotopic deposits of {sup 232}Th, {sup 233}U, {sup 235}U, {sup 238}U, {sup 237}Np, {sup 239}Pu, {sup 240}Pu, and {sup 241}Pu. Monitor chamber results at a third location were analyzed to support other experiments involving passive dosimeter fission rate determinations.
1981-05-01
FFTF (FAST FLUX TEST FACILITY) REACTOR CHARACTERIZATION PROGRAM ABSOLUTE FISSION RATE MEASUREMENTS
Energy Technology Data Exchange (ETDEWEB)
Absolute fission rate measurements using modified National Bureau of Standards fission chambers were performed in the Fast Flux Test Facility at two core locations for isotopic deposits of {sup 232}Th, {sup 233}U, {sup 235}U, {sup 238}U, {sup 237}Np, {sup 239}Pu, {sup 240}Pu, and {sup 241}Pu. Monitor chamber results at a third location were analyzed to support other experiments involving passive dosimeter fission rate determinations.
1981-05-01
PRA QUALITY IN REGULATORY DECISIONS
ASME PRA STANDARD FOR PRA. FOR NPP APPLICATION. " Provides a Standard for performing and using a. PRA. Definitions. Risk assessment ...
Neutron-induced fission cross-section of {sup 233}U in the energy range 0.5<E{sub n}< 20 MeV
Energy Technology Data Exchange (ETDEWEB)
The neutron-induced fission cross-section of {sup 233}U has been measured at the CERN n-TOF facility relative to the standard fission cross-section of {sup 235}U between 0.5 and 20MeV. The experiment was performed with a fast ionization chamber for the detection of the fission fragments and to discriminate against {alpha} -particles from the natural radioactivity of the samples. The high instantaneous flux and the low background of the n-TOF facility result in data with uncertainties of {approx} 3%, which were found in good agreement with previous experiments. The high quality of the present results allows to improve the evaluation of the {sup 233}U (n,f) cross-section and, consequently, the design of energy systems based on the Th/U cycle. (orig.)
2011-01-15
Fabrication of core demonstration experiments for irradiation in FFTF [Fast Flux Test Facility
International Nuclear Information System (INIS)
A major initiative to develop and irradiate a long-life, mixed-oxide fuel system in the Fast Flux Test Facility (FFTF) has been implemented by Westinghouse Hanford Company for the US Department of Energy. The FFTF, shown in Figures 1 and 2, is a 400 megawatt thermal, fast liquid metal reactor that tests liquid metal, space and fusion fuels and materials. The new fuel system, called the Core Demonstration Experiment (CDE) demonstrates the capability of achieving a three- to four-year life in a prototypic heterogeneous reactor environment under prototypic power and temperature conditions. This fuel system will greatly increase fuel performance and lifetime from the current standard FFTF driver fuel. New design features, fabrication development, CDE assembly fabrication, and irradiation status have been described.
1990-06-10
Utilization of low rank coals in liquefaction
Energy Technology Data Exchange (ETDEWEB)
The objective of the current MITRE study is to estimate the cost of the coal derived liquid products that result from processing low rank coals in the Wilsonville and HRI CTSL configurations. The resultant cost of liquids is then compared to liquids produced from bituminous coals. The methodology used to accomplish the above objective was to utilize the MITRE coal liquefaction cost model to assess the overall technical and economic performance of low rank coals in both the Wilsonville and HRI configurations. Actual test data from Wilsonville and HRI was used as the basis for these analyses. This test data is modified to simulate complete resid recycle extinction and to standardize the operating performance of the deashing unit. This corrected yield data is then used in the simulation models to predict the overall performance and economics of a conceptual commercial coal liquefaction ...
1991-01-01
Fast Flux Test Facility performance monitoring management information, April 1988
Energy Technology Data Exchange (ETDEWEB)
The purpose of this report is to provide management with performance data on key performance indicators selected from the FFTF Early Warning System performance indicators.
1988-05-01
Break Nodalization Influence to IAEA-SPE-4 Test Simulation
International Nuclear Information System (INIS)
A small break LOCA event simulation with no high pressure injection system available, known as International Atomic Energy Agency Standard Problem Exercise no. 4 (IAEA-SPE-4), was performed on the PMK-2 integral test facility in Budapest in 1993. This paper analyses the response of the PMK-2 facility, a model of VVER-440 nuclear power plant, using the latest released version MOD3.2.1.2 of the RELAP5 thermal-hydraulic code. After several years of the SPE-4 experiment analyses, many problems have emerged and been studied. Main goal of the present analyses was to study the main influencing parameters for adequate modelling of the hexagonal core channel with 19-rod bundle and phenomena during the core uncovery. Some influencing parameters have been identified, mostly on the primary side, but some also on the secondary side. This is exact simulation of main coolant pump coast down, hydro-accumulators water ...
1998-06-15
Replication in the Harp File System
... i3a. ... gives performance measurements for various benchmarks, and compares the performance of Harp with the standard implementation of NFS in ...
1981-07-01
International Nuclear Information System (INIS)
English 1 Feb 2009 [1 p.] United Kingdom Andelman, S Kins, Nick
2009-02-01
A - Z Index : Environmental Energy Technologies Division
Buildings Energy-Efficient Research Laboratories Energy Efficiency in Federal Facilities Energy Efficiency Standards Group Energy Efficient Windows Collaborative Energy &...
2011-07-15
This report estimates the economic and financial effects and the benefits of compliance with the proposed effluent limitations guidelines and standards for the Centralized Waste Treatment (CWT) industry. The Environmental Protection Agency (EPA) has measured these impacts in terms of changes in the profitability of waste treatment operations at CWT facilities, changes in market prices to CWT services, and changes in the quantities of waste management at CWT facilities in six geographic regions. EPA has also examined the impacts on companies owning CWT facilities (including impacts on small entities), on communities in which CWT facilities are located, and on environmental justice. EPA examined the benefits to society of the CWT effluent limitations guidelines and standards by examining cancer and non-cancer health effects of the regulation, recreational ...
1998-12-01
A Fast Ionization Chamber for Fission Cross-Section Measurements at n(_)TOF
International Nuclear Information System (INIS)
An ionization chamber with fast timing properties was built at CERN for measuring fission cross-sections of minor actinides at the n(_)TOF neutron beam. The design of this new chamber and of the front-end electronics was optimized to match the innovative features of the n(_)TOF facility, in particular the high instantaneous neutron flux and low background. For the most radioactive isotopes, a special version of the chamber, designed according to the ISO2919 standards, was built in order to comply with the radioprotection requirements at CERN. The detector and front-end electronics are here described, together with the simulated and measured response to fission fragments and #alpha#-particles. The performances of the chamber during the first measurement campaign at n(_)TOF are presented, focusing in particular on the fast time response, the good background rejection capability, low-background and high detection efficiency.
2008-09-01
Decommissioning of facility for use of radioisotopes on waste management and disposal facility
Energy Technology Data Exchange (ETDEWEB)
All the tests have been finished up in the Waste Management and Disposal Facility which has been used for the safety tests of solidified radioactive waste on sea dumping disposal. The decommissioning of this facility was performed for use of radioisotopes. This report describes the plan on decommissioning of facility for use of radioisotopes, the contamination checking methods and measurement of radioactivity, the fore case and practice for amount of generated radioactive wastes, the operation procedures for dismantlement, the safety measures, the expenses for decommissioning and so on. (author)
1999-09-01
This document provides a technical basis for the revision of chemical effluent limitations guidelines for the Steam Electric Power Industry reflecting the Best Available Technology Economically Achievable (BATEA) for existing sources, New Source Performance Standards (NSPS) and Pretreatment Standards. The analysis of pollutants and the technologies applicable to their control has been based on specific waste streams of concern.
1980-09-01
Energy Technology Data Exchange (ETDEWEB)
This Site Maintenance Plan has been developed for Pacific Northwest Laboratory's (PNL) Nonnuclear Facilities. It is based on requirements specified by US Department of Energy (DOE) Order 4330.4A, Chapter I, Change No. 4. The objective of this maintenance plan is to provide baseline information for compliance to the DOE Order 4330.4A, to identify needed improvements, and to document the planned maintenance budget for Fiscal Year (FY) 1993 and to estimate maintenance budgets for FY 1994 and FY 1995 for all PNL facilities. Using the results of the self-assessment, PNL has selected 12 of the 36 elements of the Maintenance Program defined by DOE Order 4330.4A, Chapter I, for improvement. The elements selected for improvement are: Facility Condition Inspections; Work Request (Order) System; Formal Job Planning and Estimating; Work Performance (Time) Standards; Priority System; ...
1992-09-28
Energy Technology Data Exchange (ETDEWEB)
This Site Maintenance Plan has been developed for Pacific Northwest Laboratory`s (PNL) Nonnuclear Facilities. It is based on requirements specified by US Department of Energy (DOE) Order 4330.4A, Chapter I, Change No. 4. The objective of this maintenance plan is to provide baseline information for compliance to the DOE Order 4330.4A, to identify needed improvements, and to document the planned maintenance budget for Fiscal Year (FY) 1993 and to estimate maintenance budgets for FY 1994 and FY 1995 for all PNL facilities. Using the results of the self-assessment, PNL has selected 12 of the 36 elements of the Maintenance Program defined by DOE Order 4330.4A, Chapter I, for improvement. The elements selected for improvement are: Facility Condition Inspections; Work Request (Order) System; Formal Job Planning and Estimating; Work Performance (Time) Standards; Priority System; Maintenance ...
1992-09-28
British Library Electronic Table of Contents (United Kingdom)
In Korea, the Proton Engineering Frontier Project (PEFP) is building a proton linear accelerator facility with energy up to 100MeV and a beam current of 20mA. In this study, a radiation field after shutdown in the accelerator facility of the PEFP was evaluated for the purpose of the radiation shielding by using MCNPX code. A facility modeling was performed for the accelerator tunnel building, accelerator chain, target rooms and beam experiment hall. And radiation source terms were evaluated in the facility. With this facility, model and radiation source terms, the concentration of 41Ar was evaluated and the cooling time satisfying regulation in Korea was calculated.
2007-01-01
This document presents the findings of an extensive study of the ore mining and dressing industry, for the purpose of developing effluent limitations guidelines for existing point sources and standards for performance new sources, to implement Sections 30...
1982-01-01
Job Performance Measurement in the Military: A Classification ...
... AUTHOR(S) Kavanagh, MJ; Borman, WC,; Hedge, JW; Gould, RB i3a. ... 3.5 Performance Standards, Scale Characteristics, and Scale Development ...
1987-09-01
Radiation facility with electron accelerator of the Institute for Nuclear Research of Ukraine, Kiev
International Nuclear Information System (INIS)
Characteristics of the Ukrainian NSA NRI radiation facility for scientific researches and developments of industrial radiation technology are performed. Parts of the facility, design peculiarities of technical tools are described. Biological protection of the facility and radiation protection system, transport line, systems of technical provision and radiation measurements are discussed
2003-02-01
Real-time neutron radiography system performance - Measurements and methods
Energy Technology Data Exchange (ETDEWEB)
The University of Virginia's real-time neutron radiography facility was characterized by measurement of the total neutron flux, gold/cadmium ratio, neutron/gamma ratio, and the effective collimar length-to-aperture diameter (L/D) ratio. The real-time neutron imaging system and collimator were further characterized by measuring the modulation transfer function (MTF) of the system. The collimator effectiveness was measured by using the MTF to determine the ''unparallelism'' of the neutron beam. The computer-based image processing system allowed rapid calculation of the MTF and the collimator effectiveness. The results of these measurements, using no collimator and a simple tube collimator, demonstrated the method's ability to determine the effective L/D ratio. The MTF measurement scheme provided a fast, reliable, and reproducible means of monitoring any changes in the real-time system, including both the neutron ...
1988-09-01
Real-time neutron radiography system performance - Measurements and methods
International Nuclear Information System (INIS)
The University of Virginia's real-time neutron radiography facility was characterized by measurement of the total neutron flux, gold/cadmium ratio, neutron/gamma ratio, and the effective collimar length-to-aperture diameter (L/D) ratio. The real-time neutron imaging system and collimator were further characterized by measuring the modulation transfer function (MTF) of the system. The collimator effectiveness was measured by using the MTF to determine the ''unparallelism'' of the neutron beam. The computer-based image processing system allowed rapid calculation of the MTF and the collimator effectiveness. The results of these measurements, using no collimator and a simple tube collimator, demonstrated the method's ability to determine the effective L/D ratio. The MTF measurement scheme provided a fast, reliable, and reproducible means of monitoring any changes in the real-time system, including both the neutron beam and the electronic components. This paper ...
1988-01-01
Energy Technology Data Exchange (ETDEWEB)
A testing program has been conducted by the Westinghouse Hanford Company to confirm the baseline waste form selection for use in Waste Receiving and Processing (WRAP) Module 2A. WRAP Module 2A will provide treatment required to properly dispose of containerized contact-handled, mixed low-level waste at the US Department of Energy Hanford Site in south-central Washington State. Solidification/stabilization has been chosen as the appropriate treatment for this waste. This work is intended to test cement-based, thermosetting polymer, and thermoplastic polymer solidification media to substantiate the technology approach for WRAP Module 2A. Screening tests were performed using the major chemical constituent of each waste type to measure the gross compatibility with the immobilization media and to determine formulations for more detailed testing. Surrogate materials representing each of the eight waste types were prepared in the laboratory. These surrogates were then ...
1993-10-01
Development of an analysis rule of diagnosis error for standard method of human reliability analysis
International Nuclear Information System (INIS)
This paper presents the status of development of Korea standard method for Human Reliability Analysis (HRA), and proposed a standard procedure and rules for the evaluation of diagnosis error probability. The quality of KSNP HRA was evaluated using the requirement of ASME PRA standard guideline, and the design requirement for the standard HRA method was defined. Analysis procedure and rules, developed so far, to analyze diagnosis error probability was suggested as a part of the standard method. And also a study of comprehensive application was performed to evaluate the suitability of the proposed rules.
2003-10-01
The report details the economic impact of two alternative regulatory options; a Treated Discharge Option and a Zero Discharge Option on facilities that would have to comply with the regulations as part of the reproposal of effluent limitations and standar...
1992-01-01
This document is a technical background document for proposed regulations to limit effluent discharges to waters of the United States and introductions of pollutants into publicly owned treatment works from facilities engaged in porcelain enameling. The p...
1981-01-01
Energy Technology Data Exchange (ETDEWEB)
A brief overview of the conceptual design of a solar central receiver system integrated with an existing cogeneration facility is provided. A synopsis of the performance and economic evaluation, and an assessment of the concept from the site owner's perspective are given.
1981-08-07
Industrial experience with an intelligent AC/DC standard
Energy Technology Data Exchange (ETDEWEB)
AC/DC voltage standards based entirely on solid-state references used as secondary, working, or transfer standards is widespread, although metrological performance is typically defined only via comparison with a higher level standard. The present report shows the improvements of the output metrological characteristics of an ac/dc calibrator by establishing three internal hierarchical levels of dc voltage references and by constant calibration of ac measuring circuits.
1989-04-01
This document presents the findings of a study of the Ink Manufacturing Industry for the purpose of developing effluent limitations and standards, and pretreatment standards for existing and new sources to implement Sections 301, 304, 306, 307 and 501 of ...
1979-01-01
Coilgun Launcher for Nanosatellites
Energy Technology Data Exchange (ETDEWEB)
Nanosatellite space launches could significantly benefit from an electrically powered launch complex, based on an electromagnetic coil launcher. This paper presents results of studies to estimate the required launcher parameters and some fixed facility issues. This study is based on electromagnetic launch, or electromagnetic gun technology, which is constrained to a coaxial geometry to take advantage of the efficiency of closely-coupled coils. A baseline configuration for analysis considers a payload mass of 10 kg, launch velocity of 6 km/s, a second stage solid booster for orbital insertion, and a payload fraction of about 0.1. The launch facility is envisioned as an inclined track, 1-2 km in length, mounted on a hillside at 25 degrees aimed in the orbital inclination of interest. The launcher energy and power requirements fall in the range of 2000 MJ and 2 MW electric. This energy would be supplied by 400 modules of energy storage and ...
1999-03-23
Effectively managing nuclear risk through human performance improvement
International Nuclear Information System (INIS)
Full text: The US commercial nuclear industry has just completed an outstanding decade of plant performance. Safety levels and electric production are at unprecedented high levels and continue to exceed even high industry goals. Nuclear energy continues to keep the highest priority on performance improvement programs and highly trained/qualified people that maintain its record setting safety and reliability of operations. While the industry has maintained a consistently high level of performance, the advent of deregulation and the consolidation of NPP ownership, as well as the current climate of concern about both rising energy costs and availability of power, has raised the standard for nuclear energy's level of competitiveness in today's market place. The resulting challenge is how to more effectively manage risk and improve performance even further in a generally high ...
High Exposure Facility Technical Description
Energy Technology Data Exchange (ETDEWEB)
The High Exposure Facility is a collimated high-level gamma irradiator that is located in the basement of the 318 building. It was custom developed by PNNL back in 1982 to meet the needs for high range radiological instrument calibrations and dosimeter irradiations. At the time no commercially available product existed that could create exposure rates up to 20,000 R/h. This document is intended to pass on the design criteria that was employed to create this unique facility, while maintaining compliance with ANSI N543-1974, "General Safety Standard for Installations Using Non-Medical X-Ray and Sealed Gamma-Ray Sources, Energies up to 10 MeV."
2008-02-12
Energy Technology Data Exchange (ETDEWEB)
This document, the Standards/Requirements Identification Document (S/RID) Phase I Assessment Report for the subject facility, represents the results of an Administrative Assessment to determine whether S/RID requirements are fully addressed by existing policies, plans or procedures. It contains; compliance status, remedial actions, and an implementing manuals report linking S/RID elements to requirement source to implementing manual and section.
1996-09-30
Non-standard antineutrino interactions at Daya Bay
We study the prospects of pinning down the effects of non-standard antineutrino interactions in the source and in the detector at the Daya Bay neutrino facility. It is well known that if the non-standard interactions in the detection process are of the same type as those in the production, their net effect can be subsumed into a mere shift in the measured value of the leptonic mixing angle theta_13. Relaxing this assumption, the ratio of the antineutrino spectra measured by the Daya Bay far and near detectors is distorted in a characteristic way, and good fits based on the standard oscillation hypothesis are no longer viable. We show that, under certain conditions, three years of Daya Bay running can be sufficient to provide a clear hint of non-standard neutrino physics.
2011-01-01
The report discusses the capabilities of equipment vendors to supply and install the quantity of flue gas desulfurization systems required to meet alternative standards for coal-fired steam generators. It analyzes limiting factors affecting supply capabilities (such as the availa...
Development of an irradiation system for a small size continuous run multipurpose gamma irradiator
International Nuclear Information System (INIS)
The Radiation Technology Center from IPEN-CNEN/SP, Brazil, developed a revolutionary design and national technology, a small-sized continuous run and multipurpose industrial gamma irradiator, to be used as a demonstration facility for manufacturers and contract service companies, which need economical and logistical in-house irradiation system alternatives. Also, to be useful for supporting the local scientific community on development of products and process using gamma radiation, assisting the traditional and potential users on process validation, training and qualification of operators and radioprotection officers. The developed technology for this facility consists of a continuous tote box transport system, comprising a single concrete vault, where the automated transport system of products inside and outside of the irradiator utilizes a rotating door, integrated with the shielding, avoiding the traditional maze configuration. Covering 76 ...
Energy Technology Data Exchange (ETDEWEB)
The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, has been constructed to be a repository for transuranic (TRU) radioactive wastes generated from the US defense activities. In order to use WIPP as a repository for permanent disposal of TRU waste, the US Department of Energy (DOE) has to demonstrate compliance with the Standards for the Management and Disposal of Spent Nuclear Fuel, High Level and Transuranic Radioactive Wastes'' promulgated by the US Environmental Protection Agency (EPA) in the US Code of Federal Regulations 40 CFR Part 191. The DOE initially plans to perform experiments with a small quantity of waste at WIPP and would like to bring additional quantities for operational demonstration'', before determining whether WIPP is to be a repository for permanent disposal. There are serious problems in pursuing this course of action from an operational point of view. It would ...
1991-01-01
Remediation process technology for ground water
Energy Technology Data Exchange (ETDEWEB)
The operation of industrial facilities has generally resulted in contamination of the surrounding soils and ground water. A variety of methods have been proposed for the remediation of contaminated sites. This paper presents new process technology that is capable of performing treatment on ground water or soil washing leachates. The process is targeted to treat low levels of radioactivity, organics and heavy metals present in the aqueous solutions, to be easily transported and provide simple operation on-site and provide an effluent that meets the specified discharge quality. The purification process involves sequential chemical treatment and filtration. The paper will describe the development of the technology and review the current progress in its use to remediate contaminated sites at Chalk River. The application of the process technology has demonstrated that the ambitious goal of setting the effluent targets to meet the drinking water ...
1993-12-31
Remediation process technology for ground water
International Nuclear Information System (INIS)
The operation of industrial facilities has generally resulted in contamination of the surrounding soils and ground water. A variety of methods have been proposed for the remediation of contaminated sites. This paper presents new process technology that is capable of performing treatment on ground water or soil washing leachates. The process is targeted to treat low levels of radioactivity, organics and heavy metals present in the aqueous solutions, to be easily transported and provide simple operation on-site and provide an effluent that meets the specified discharge quality. The purification process involves sequential chemical treatment and filtration. The paper will describe the development of the technology and review the current progress in its use to remediate contaminated sites at Chalk River. The application of the process technology has demonstrated that the ambitious goal of setting the effluent targets to meet the drinking water ...
1993-09-05
Production of hydrogen by radiolysis
Energy Technology Data Exchange (ETDEWEB)
The possibility of obtaining high yields of hydrogen through the exposure of calcium hydroxide to natural uranium fission fragments is confirmed experimentally. The amounts of hydrogen obtained in some experiments were determined not only from the mass-spectrometry data, but also with the use of standard chemical analysis methods. The radiolytic hydrogen yield averaged over six independent experiments comprises 20.41 hydrogen molecules per 100 eV of absorbed fission fragment energy. The corresponding energy efficiency makes up to 60.62. Since on interaction with water or water vapor calcium hydroxide enters into the exothermal reaction to liberate 15.6 kcal/mole, it can easily be regenerated; this was attested to by one of irradiation experiments. Therefore, in the long run, we are dealing with a radiolytic decomposition of water at low temperatures or at temperatures readily available with modern reactor engineering techniques. Comparison of the present data with ...
1998-07-01
Energy Technology Data Exchange (ETDEWEB)
The objective of this project was to develop a explosion suppression system capable to confine and extinguish gas explosions of the type produced in sub level caving faces when blasting to the coal pillar. Existing systems, such as triggered barriers, were considered not to be valid because of size, weight, cost, and other operational constraints. The research activities have been focused in the development of a mixed water/air spray system that should be manually activated some second before blasting. Two prototypes have been developed and tested, the first one using nozzle operating at the standard ranges of pressure that are normally available in underground coal mines, and a second one based in high-pressure nozzles. In this case, bottles containing a pressurized air/water mixtures are required. The works carried out included theoretical studies, hydraulic nozzles characterization, and modelling of the explosion phenomena using the AutoReaGas code. Besides, ...
1999-11-01
Energy Technology Data Exchange (ETDEWEB)
The Outstanding Achievement Award in Water Pollution Control' is intended to recognize the water pollution control program that best demonstrates achieving significant, lasting, and measurable excellence in water-quality improvement in preventing water-quality degradation in a region, basin, or water body. This article is about the 1991 Award. This year, WPCF honored Los Angeles Hyperion Treatment Plant with a citation of outstanding achievement. To qualify for this honor, Hyperion has remarkably improved the quality of wastewater discharged to Santa Monica Bay since 1985. Capital programs developed by Los Angeles to achieve this rapid improvement, coined the Hyperion Improvement Program (HIP), reflect the city's commitment to protect the valuable resource of Santa Monica Bay. The HIP was conceived in 1986 to cease sludge ocean disposal by the end of 1987 and expedite effluent quality improvement before 1991, when the full secondary expansion is scheduled for ...
1991-11-01
Current issues of nuclear equipment standardization in Romania
International Nuclear Information System (INIS)
Standardization enhances: international cooperation; development of new nuclear techniques and technologies; characterization and checking procedures of equipment; sharing a common terminology. A historical sketch is given focussing: inception of standardization in electro-techniques at international scale; organization of the International Electrotechnical Commission, IEC; - current aspects of nuclear equipment standardization; activity of seven working groups devoted to nuclear reactor equipment; activity of seven groups working on radioprotection equipment; activity of four groups working on nuclear equipment. ISO organization and present issues concerning the nuclear technology development in Romania. It is presented the activity in the frame of CENELEC, CLC/TC45, for endorsing the IEC/TC45B standards. In 2007 a CENELEC/ BTT 127-1 working commission was formed to enhance assimilation of IEC /TC45 A ...
2009-10-12
International Nuclear Information System (INIS)
This study evaluates the degree to which surface impoundments at licensed facilities comply with significant changes in NRC requirements initiated by enactment of EPA's final environmental standards for uranium recovery facilities (40 CFR Part 192). Impoundment liner requirements, ground-water protection standards, ground-water monitoring and corrective action programs, and site closure standards are the most significant regulatory modifications. The compliance status of 30 conventional mills and 31 in-situ mines is determined from a review of Nuclear Regulatory Commission and agreement state docket files through November, 1983. Results of this review show that a majority of conventional uranium mill tailings management systems are deficient with respect to liner requirements for new impoundments or proposed expansions to existing impoundments, as well as with respect to some ...
Air pollutants emissions from waste treatment and disposal facilities.
This study examined the atmospheric pollution created by some waste treatment and disposal facilities in the State of Kuwait. Air monitoring was conducted in a municipal wastewater treatment plant, an industrial wastewater treatment plant established in a petroleum refinery, and at a landfill site used for disposal of solid wastes. Such plants were selected as models for waste treatment and disposal facilities in the Arabian Gulf region and elsewhere. Air measurements were made over a period of 6 months and included levels of gaseous emissions as well as concentrations of volatile organic compounds (VOCs). Samples of gas and bioaerosols were collected from ambient air surrounding the treatment facilities. The results obtained from this study have indicated the presence of VOCs and other gaseous pollutants such as methane, ammonia, and hydrogen sulphide in air surrounding the waste treatment and disposal ...
2006-01-01
Results of 1st regular inspection of No.2 unit in Sendai Nuclear Power Plant
International Nuclear Information System (INIS)
This report presents results of the 1st regular inspection of the No.2 unit of the Sendai Nuclear Power Plant. It was carried out during the period from September 22, 1986, to December 24, 1986. The inspection covered the main unit of the nuclear reactor, facilities for the nuclear reactor cooling system, facilities for the instrumentation control system, fuel facilities, radiation control facilities, disposal facilities, nuclear reactor containment facilities, and emergency power generation system. Checking of appearance, disassemblage, leak and functions-performance of these facilities was conducted and no abnormalities were found. All operations involved in the inspection were performed under conditions within the permissible dose as specified in the applicable laws. No major modification work was ...
1987-01-01
Results of 1st regular inspection of No. 2 unit in Sendai Nuclear Power Plant
Energy Technology Data Exchange (ETDEWEB)
This report presents results of the 1st regular inspection of the No. 2 unit of the Sendai Nuclear Power Plant. It was carried out during the period from September 22, 1986, to December 24, 1986. The inspection covered the main unit of the nuclear reactor, facilities for the nuclear reactor cooling system, facilities for the instrumentation control system, fuel facilities, radiation control facilities, disposal facilities, nuclear reactor containment facilities, and emergency power generation system. Checking of appearance, disassemblage, leak and functions-performance of these facilities was conducted and no abnormalities were found. All operations involved in the inspection were performed under conditions within the permissible dose as specified in the applicable laws. No major modification work ...
1987-09-01
Energy Technology Data Exchange (ETDEWEB)
Since 1976, the Nuclear Engineering Laboratory of the Technical Research Centre of Finland and Lappeenranta University of Technology have cooperated in the field of nuclear reactor thermal-hydraulics. During these years, a series of experimental facilities (REWET-I, -II, -III, VEERA) simulating pressurized water reactors (PWRs) have been built. The newest facility, PACTEL (Parallel Channel Test Loop), is an experimental out-of-pile facility designed to simulate the major components and system behaviour of a commercial PWR during postulated small and medium size break loss-of-coolant accidents (LOCAs), natural circulation and operational transients. A PACTEL natural circulation experiment has been carried out as an OECD/NEA international standard problem ISP 33. (2 refs., 3 figs., 2 tabs.).
1993-12-31
Development of calibration facility for radiation protection monitoring instruments
International Nuclear Information System (INIS)
Exposure control at the operating Nuclear Power Station is a major concern. The challenging task of meeting the International standards in the field of radiation protection is the calibration of the radiation monitoring instruments and interpretation of personnel and area monitoring results. Correct interpretation is based on accurate calibration of radiation measuring instruments. The reliability and accuracy of the measurements are also partly based on the procedures applied in calibration. Inadequate calibration can cause large errors in dose estimation in complete dose rate range and energy range. Semiautomatic calibration facility established at TAPS 3 and 4 for radiation monitoring instruments. Objective of calibration facility is (a) Ensure instruments are working properly (b) calibration adjustment and (c) in case without calibration adjustment to reveal the error involved. The calibration ...
2008-11-19
International Nuclear Information System (INIS)
The 2nd periodical inspection was carried out on the asphalt solidification facility and the incinerator in Unit 2 of the Sendai Nuclear Power Station from November 5 to 28, 1985. Inspection was made in radiation control facility and disposal facility. By external appearance, disassembly, function and performance tests there were observed no abnormalities. The personnel exposure doses during the inspection were below the permissible level. In the inspection, improvement etc. works were not done. (Mori, K.).
1986-01-01
International Nuclear Information System (INIS)
The regular inspection of No.2 plant in Sendai Nuclear Power Station was carried out from January 7 to February 8, 1985. The summary of the results of this regular inspection is as follows. The facilities as the object of inspection were radiation control facilities and waste facilities. On these facilities as the object of inspection, the appearance, disassembling, functional, performance and other inspections were carried out, and as the results, abnormality was not found at all. The works related to this regular inspection were accomplished within the range of the allowable radiation dose based on the relevant laws. (Kako, I.).
1986-01-01
Minimally Invasive Orthopedic Surgery: Arthroscopy
UK PubMed Central (United Kingdom)
Arthroscopy, a minimally invasive alternative to standard open surgical techniques and now the most commonly performed orthopedic surgical procedure, was one of the greatest advances in orthopedic surgery...Full Text Available
2000-07-01
EPA - Stormwater Discharges from Construction Activities
discharges. Proposed Stormwater ELG from Construction Sites - EPA has proposed effluent limitations guidelines (ELGs) and new source performance standards (NSPS) to control...
2011-10-14
Avenger Team Performance During Engagement Operations ...
... MOPP I3A f. Kl Figure 12. ... Table 13 contains the means, standard deviations, and number of observations for both clothing conditions. ...
1993-06-01
The PANDA facility and first test results
International Nuclear Information System (INIS)
The PANDA test facility at the Paul Scherrer Institute is used to study the long-term performance of the Simplified Boiling Water Reactor's passive containment cooling system. The PANDA tests demonstrate performance on a larger scale than previous tests and examine the effects of any non-uniform spatial distributions of steam and non-condensable gases in the system. The facility is in 1:1 vertical scale and 1:25 scale for volume, power etc. Extensive facility characterization tests and steady-state passive containment condenser performance tests are presented. The results of the base case test of a series of transient system behaviour tests are reviewed. The first PANDA tests exhibited reproducibility, and indicated that the Simplified Boiling Water Reactor's containment is likely to be favorably responsive and highly robust to changes in the thermal transport ...
Energy Technology Data Exchange (ETDEWEB)
A performance assessment of the operating Solid Waste Storage Area 6 (SWSA 6) facility for the disposal of low-level radioactive waste at the Oak Ridge National Laboratory has been prepared to provide the technical basis for demonstrating compliance with the performance objectives of DOE Order 5820.2A, Chapter 111.2 An analysis of the uncertainty incorporated into the assessment was performed which addressed the quantitative uncertainty in the data used by the models, the subjective uncertainty associated with the models used for assessing performance of the disposal facility and site, and the uncertainty in the models used for estimating dose and human exposure. The results of the uncertainty analysis were used to interpret results and to formulate conclusions about the performance assessment. This paper discusses the approach taken in ...
1994-12-31
Radiological performance assessment for the E-Area Vaults Disposal Facility
Energy Technology Data Exchange (ETDEWEB)
This report is the first revision to ``Radiological Performance Assessment for the E-Area Vaults Disposal Facility, Revision 0'', which was issued in April 1994 and received conditional DOE approval in September 1994. The title of this report has been changed to conform to the current name of the facility. The revision incorporates improved groundwater modeling methodology, which includes a large data base of site specific geotechnical data, and special Analyses on disposal of cement-based wasteforms and naval wastes, issued after publication of Revision 0.
2000-04-11
Energy Technology Data Exchange (ETDEWEB)
This study analyzes the economic impact that could result from the application of effluent standards and limitations issued under Sections 301, 304, 306, 307 of the Clean Water Act to the pulp, paper, and paperboard industry, including builders' paper and roofing felt manufacturing.
1980-12-01
International Nuclear Information System (INIS)
The EPA proposed effluent limitations guidelines and standards for the offshore segment of the oil and gas industry on August 26, 1985. On November 26, 1990, and March 13, 1991, the Agency reproposed effluent limitations guidelines and standards for both drilling and production wastes. The report is primarily concerned with the total annualized cost incurred by the offshore oil and gas industry in complying with the regulations.
1993-01-01
Radwaste Drum Assay Technology by Segmented Gamma Scanning System
Energy Technology Data Exchange (ETDEWEB)
Nuclear Act of Korea requires the manifest of low and intermediate level radioactive waste generated from nuclear power plants and other nuclear facilities prior to deliver to a disposal sites. Individual history records of the radioactive waste should be described the information about the activity of nuclides in the drum, total activity, weight, the type of waste. So a fully automated nuclide analysis assay system(non-destructive) of a radwaste drum was developed. For the nuclides that could not be analysed directly by MCA, the activities of the representative {gamma}-emitters(Cs-137, Co-60) contained in the drum were measured by using that system. Then the scaling factors were used to calculate the activities of {alpha} - and {beta}-emitters. This assay system divided a drum into 8 segments, a segment into 8 sectors to minimize analysis error, and used several methods(transmission ratio, differential peak absorption, mean density correction), with a individual ...
2009-01-15
Current status of siting a new near surface repository in Romania
International Nuclear Information System (INIS)
Full text: The site selection process for a near surface repository dedicated for the radioactive waste resulted from the Cernavoda NPP operation and decommissioning started early in 90's. Each site selection stage included the collection of data from specific field and laboratory works as well as the appropriate safety performance evaluation. In order to assess/confirm the performance of the natural barrier of the Saligny site, the radionuclide concentration in the disposal system compartments has been evaluated, as complementary safety indicator of repository. The siting process was made in accordance with national and international regulations and standards and using a conceptual design similar to those used at L'Aube (France), ElCabril (Spain) or Mohovce (Slovak Republic). ANDRAD, the Romanian waste management organization that has continued the siting process in the last three years applied and obtained a partial ...
2009-05-27
Energy Technology Data Exchange (ETDEWEB)
The performance of binary geothermal power plants can be improved through the proper choice of a working fluid, and optimization of component designs and operating conditions. This paper reviews the investigations at the Idaho National Engineering Laboratory (INEL) which are examining binary cycle performance improvements: for moderate temperature (350 to 400 F) resources with emphasis on how the improvements may be integrated into design of binary cycles. These investigations are examining performance improvements resulting from the supercritical vaporization of mixed hydrocarbon working fluids and achieving countercurrent integral condensation with these fluids, as well as the modification of the turbine inlet state points to achieve supersaturated turbine vapor expansions. For resources where the brine outlet temperature is restricted, the use of turbine exhaust recuperators is examined. The baseline plant used to ...
1989-03-21
Energy Technology Data Exchange (ETDEWEB)
Technical Development Document supporting proposed water discharge regulations for the Coal Mining Industry authorized by the Clean Water Act. Proposed regulations include revised best practicable technology limitations, best available technology limitations and new source performance standards for the Coal Mining Industry. Industry operations include: coal preparation and amillary operations, active mining, F bituminous, anthracite and lignite coal, and the reclamation phase of mining.
1981-01-01
Monitoring processes and measuring the effectiveness of the management system
International Nuclear Information System (INIS)
This document presents the way which the 8th principle of the quality management system 'Process approach' is applied, the principle that is identified and used by international standard ISO 9000. In order to understand the evolution of the management system requirements, as used today in different activities namely, industry, services, and nuclear activities, the authors present an evolution of the quality concept and its traceability to different standards, applicable in time. There are described the requirements of ISO 9001 standard, that represents the most widely spread model for modern organization management and the IAEA concerns related to integration of the above standard requirements into the most recent safety IAEA standard 'The Management System for facilities and activities'. The IAEA Safety Standard GS-R-3 describes a ...
2009-10-12
Waste Receiving and Processing Facility Module 2A: Advanced Conceptual Design Report. Volume 1
Energy Technology Data Exchange (ETDEWEB)
This ACDR was performed following completed of the Conceptual Design Report in July 1992; the work encompassed August 1992 to January 1994. Mission of the WRAP Module 2A facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities the Category 1 and 3 contact handled low-level radioactive mixed wastes that are currently in retrievable storage at Hanford and are forecast to be generated over the next 30 years by Hanford, and waste to be shipped to Hanford from about DOE sites. This volume provides an introduction to the ACDR process and the scope of the task along with a project summary of the facility, treatment technologies, cost, and schedule. Major areas of departure from the CDR are highlighted. Descriptions of the facility layout and operations are included.
1994-03-01
International Nuclear Information System (INIS)
This document defines the services the Waste Sampling and Characterization Facility (WSCF) shall provide Effluent Monitoring (EM) throughout the calendar year for analysis. The internal memo contained in Appendix A identifies the samples Em plans to submit for analysis in CY-1995. Analysis of effluent (liquid and air discharges) and environmental (air, liquid, animal, and vegetative) samples is required using standard laboratory procedures, in accordance with regulatory and control requirements. This report describes regulatory reporting requirements and WSCF services and data quality objectives.
Multi-frequency binary sequence testing at FFTF [Fast Flux Test Facility
International Nuclear Information System (INIS)
The multi-frequency binary sequence experimental technique has been implemented at the Fast Flux Test Facility for routine surveillance activities. The frequency content of the standard rod-movement sequence has been shown to be sufficient to normalize the data at moderate frequencies. This obviates the need for auxiliary calibration measurements and provides the reactivity worth of the test control rod. Analyses of a series of tests conducted in 1986 illustrate that the rod worths inferred from the tests are consistent with zero-power measurements. Also, the dependence of the prompt feedback time constant on reactor conditions was determined.
1988-09-18
Energy Technology Data Exchange (ETDEWEB)
This document includes the following topics: Background; Data Collection; Scope/Applicability of the Proposed Regulation; Description of the Industry; Industry Subcategorization; Pollutants of Concern for the Centralized Waste Treatment Industry; Pollutants Selected for Regulation; Wastewater Treatment Technologies; Regulatory Options Considered and Selected for Basis of Regulation; Long-Term Averages, Variability Factors, and Limitations and Standards; Cost of Treatment Technologies; Pollutant Loading and Removal Estimates; Non-Water Quality Impacts; Implementation; Analytical Methods and Baseline Values; List of Definitions; List of Acronyms; Appendix A--Pollutant Groups; Appendix B--Listing of Characerization Data From Non-Hazardous Oils Facilities; Appendix C--Listing of Daily Influent and Effluent Measuements; Appendix D--Facility-Specific Compliance Costs; Appendix E--Attachements to Chapter 10; and Appendix ...
1998-12-01
Regulatory quality assurance requirements for the operation of nuclear R and D facilities in Korea
International Nuclear Information System (INIS)
Full text: Korea Atomic Energy Research Institute (KAERI) has many R and D facilities in operation. including HANARO research reactor, radioactive waste treatment facility (RWTF), post-irradiation examination facility (PIEF) and irradiated material test facility (IMEF). Recently. nation-wide interest is focused on the safety and security of major industrial facilities. Safe operation of nuclear facilities is imperative because of the consequence of public disaster by radiological release/contamination, in case of an accident. Recently, Ministry of Science and Technology (MOST) of the Korean government announced amendments of Atomic Energy laws to enforce requirements of the physical protection and radiological emergency. All provisions on nuclear safety regulation and radiation protection are entrusted to the Atomic Energy Act(AEA). The Act is enacted as the ...
2006-10-15
Acceptance test report for the Westinghouse 100 ton hydraulic trailer
Energy Technology Data Exchange (ETDEWEB)
The SY-101 Equipment Removal System 100 Ton Hydraulic Trailer was designed and built by KAMP Systems, Inc. Performance of the Acceptance Test Procedure at KAMP`s facility in Ontario, California (termed Phase 1 in this report) was interrupted by discrepancies noted with the main hydraulic cylinder. The main cylinder was removed and sent to REMCO for repair while the trailer was sent to Lampson`s facility in Pasco, Washington. The Acceptance Test Procedure was modified and performance resumed at Lampson (termed Phase 2 in this report) after receipt of the repaired cylinder. At the successful conclusion of Phase 2 testing the trailer was accepted as meeting all the performance criteria specified.
1995-03-06
Open test assembly (OTA) shear demonstration testing work/test plan
Energy Technology Data Exchange (ETDEWEB)
This document describes the development testing phase associated with the OTA Shear activity and defines the controls to be in place throughout the testing. The purpose of the OTA Shear Program was to provide equipment that is needed for the processing of 40 foot long, sodium wetted, irradiated core components previously used in the FFTF reactor to monitor fuel and materials tests. There are currently 15 of these OTA test stalks located in the Test Assembly Conditioning Station (TACS) inerted vault. These need to be dispositioned for a shutdown mission to eliminate this highly activated, high dose inventory prior to turnover to the ERC since they must be handled by remote operations. These would also need to be dispositioned for a restart mission to free up the vault they currently reside in. The waste handling and cleaning equipment in the J33M Cell was designed and built for the handling of reactor components up to the standard 12 foot length. This program will ...
1998-07-16
Non-Traditional In Situ Vitrification - A Technology Demonstration at Los Alamos National Laboratory
Energy Technology Data Exchange (ETDEWEB)
The Department of Energy (DOE) Subsurface Contamination Focus Area (SCFA) sponsored a technology demonstration of non-traditional in situ vitrification (NTISV) at Los Alamos National Laboratory (LANL). The project team for this demonstration included MSE Technology Applications, Inc., Geosafe Corporation, and LANL. The technology demonstration involved the performance of two large-scale test melts. The first, referred to as the ''cold'' test, was performed on a simulated absorption bed that contained surrogate contaminants. The cold test was conducted in April 1999. The second demonstration, referred to as the ''hot'' test, took place at LANL's Material Disposal Area (MDA) V in April 2000. The hot test was conducted on a portion of an absorption bed that received radionuclide and metal-contaminated wastewater from a laundry facility and a ...
2003-02-25
FFTF [Fast Flux Test Facility] management
International Nuclear Information System (INIS)
Fuel Management at the Fast Flux Test Facility (FFTF) involves more than just the usual ex-core and in-core management of standard fuel and non-fuel components between storage locations and within the core since it is primarily an irradiation test facility. This mission involves testing an ever increasing variety of fueled and non-fueled experiments, each having unique requirements on the reactor core as well as having its own individual impact on the reload design. This paper describes the fuel management process used by the Westinghouse Hanford Company Core Engineering group that has led to the successful reload design of nine operating cycles and the irradiation of over 120 tests.
1987-09-13
Safety considerations in the application of tension leg platforms and spar based systems
Energy Technology Data Exchange (ETDEWEB)
This paper is focused on TLP and Spar technology as applied to floating production applications. In particular, safety considerations as related to classification and certification requirements are addressed. This covers hull structures, marine systems, production facilities and the relevant mooring systems for each platform type from design approval on through construction, installation and ultimately the ongoing maintenance of the platform to acceptable standards throughout its operating life. The experience of the American Bureau of Shipping with these platforms will be utilized in supporting the practical application of classification and regulatory standards to ensure safe operations and concluding that use of such standards in conjunction with an experienced classification society provides a substantial benefit to companies utilizing these technologies. (author)
1998-07-01
Energy Technology Data Exchange (ETDEWEB)
The report identifies and analyzes the economic impacts of water pollution control regulations on the battery manufacturing industry. These regulations include effluent limitations and standards based on BPT (best practical control technology currently available), BAT (best available technology economically achievable), PSES (pretreatment standards existing sources), NSPS (new source performance standards), and PSNS (pretreatment standards new sources), that have been promulgated under authority of Sections 301, 304, 306, 307, 308, and 501 of the Federal Water Pollution Control Act, as Amended (the Clean Water Act). The primary economic impact variables of interest include price changes, plant closures, substitution effects, changes in employment, shifts in the balance of foreign trade, changes in industry profitability, structure, and competition, and impacts on small business.
1984-01-01
International Nuclear Information System (INIS)
The PANDA test facility at PSI in Switzerland is used to study the long-term Simplified Boiling Water Reactor (SBWRT) Passive Containment Cooling System (PCCS) performance. The PANDA tests demonstrate performance on a larger scale than previous tests and examine the effects of any non-uniform spatial distributions of steam and noncondensables in the system. The PANDA facility is in 1:1 vertical scale, and 1:25 'system' scale (volume, power, etc.). Steady-state PCCS condenser performance tests and extensive facility characterization tests have already been conducted. A series of transient system behavior tests have been completed by end of 1995. Results from the first three transient tests (M3 series) are reviewed. The first PANDA tests exhibited reproducibility, and indicated that the SBWR containment is likely to be favorably responsive and highly robust to ...
Energy Technology Data Exchange (ETDEWEB)
In accordance with federal legislation, the U.S. Department of Energy (DOE) has conducted a project to demonstrate use of its Energy Conservation Voluntary Performance Standards for Commercial and Multi-Family High-Rise Residential Buildings; Mandatory for New Federal Buildings; Interim Rule (referred to in this report as DOE-1993). A key requisite of the legislation requires DOE to develop commercial building energy standards that are cost effective. During the demonstration project, DOE specifically addressed this issue by assessing the impacts of the standards on (1) construction costs, (2) builders (and especially small builders) of multi-family, high-rise buildings, and (3) the ability of low-to moderate-income persons to purchase or rent units in such buildings. This document reports on this project.
1993-12-01
Risk evaluation system for facility safeguards and security planning
International Nuclear Information System (INIS)
The Risk Evaluation System (RES) is an integrated approach to determining safeguards and security effectiveness and risk. RES combines the planning and technical analysis into a format that promotes an orderly development of protection strategies, planning assumptions, facility targets, vulnerability and risk determination, enhancement planning, and implementation. In addition, the RES computer database program enhances the capability of the analyst to perform a risk evaluation of the facility. The computer database is menu driven using data input screens and contains an algorithm for determining the probability of adversary defeat and risk. Also, base case and adjusted risk data records can be maintained and accessed easily.
1987-07-12
A study on the design method of multi tunnels in geological disposal facility
International Nuclear Information System (INIS)
In the geological disposal facility of the high-level radioactive waste, a group of galleries is designed in parallel at the depth of more than 300 m below surface. This is an unprecedented structure in the field of conventional engineering, and it is necessary to take this characteristic into consideration in the design of the galleries. In the geological disposal facility, as well as ensuring the dynamic stability of the gallery during construction and operational periods, it is necessary to evaluate the EDZ adequately for long-term stability after the closure. In this study, analysis of the 'multi tunnels model' which represents the whole gallery group was performed and the results about the outbreak behavior of EDZ were summarized. (author)
2008-01-01
Energy Technology Data Exchange (ETDEWEB)
The document describes the statistical analyses of data on pollutant loadings in effluent wastestreams from pulp, paper, and paperboard facilities. Included are the analyses that support the revised subcategorization and proposed effluent limitations for biochemical oxygen demand and total suspended solids based upon the best practicable control technology currently available.
1993-11-01
Intercomparison of irradiance measurements based on WRR and ETL irradiance scales
Energy Technology Data Exchange (ETDEWEB)
We report the corrected intercomparison of the World Radiometer Reference (WRR) irradiance scale and the Electrotechnical Laboratory (ETL) spectral irradiance scale. In addition, we confirm the intercomparison precision using the test facility where the irradiance of ETL 500 W standard lamp can be measured directly with the cavity radiometer. The results showed that the irradiance based on the WRR scale was 0.5-0.7% lower than the one based on the ETL scale
1997-10-14
The report consist of the following appendices: A. Cost annualization model; B. Facility level analysis; C. Market model methodology; D. Summary of Demand and Supply Elasticity Literature; E. Sensitivity analysis; and F. Cost effectiveness analysis.
2002-01-01
Development of technical information basis of aging management for nuclear power plants
International Nuclear Information System (INIS)
In order to implement effective safety regulations on aging management for reactor facilities etc., the information on important technology issues, the latest technical knowledge including evaluation technology, test and research outcomes, related codes and standards, regulation information, operation experiences such as accidents and trouble, etc. with respect to aging-induced deterioration in and outside Japan and in other industries, were collected, organized and evaluated. (author)
2007-08-01
Subcriticality calculations for the FFTF reverse approach to critical experiment
The reverse approach to critical (RAC) experiments were performed in the ZPR-IX critical facility at Argonne National Laboratory. One of the major objectives of this project is to determine the adequacy of the low-level flux monitor (LLFM) detectors for initial loading of the Fast Flux Test Facility (FFTF). 5 references. (auth)
1975-01-01
High temperature materials experience at the Central Receiver Test Facility
During four years of operation at the Central Receiver Test Facility (CRTF) ceramics have performed well in cyclic solar flux densities of less than 30 W/cm/sup 2/. Above 100 W/cm/sup 2/, serious limitations exist. Important application considerations include: the geometry, cyclic and long time exposures, flux density gradients, thermal shock, weathering, and soiling.
1982-01-01
Calculation of neutron source strength in Fast Flux Test Facility fuel as a function of irradiation
Energy Technology Data Exchange (ETDEWEB)
A method of calculating the neutron source strength in irradiated Fast Flux Test Facility (FFTF), fuel has been developed and is presented in this paper. This method has been used to perform calculations in support of the reactivity monitoring of the FFTF reactor by the modified source multiplication method during refueling operations. 31 refs.
1981-08-01
Energy Technology Data Exchange (ETDEWEB)
Since June 1997 the standards/specifications and inspection/certification of various products in Japan have been reviewed by Ministries and Agencies, with the aim of reducing direct government intervention to a necessary minimum and creating a free and fair socio-economic system that is fully opened to the international community and based on the rules of self-responsibility and market principles. Reflecting this policy the administrative regulations which prescribe technical standards as specific requirements have been revised by degrees into performance prescriptions. Detailed provisions in ordinances and notices have been abolished gradually to utilize voluntary standards and rules. In the nuclear energy field voluntary standards are being developed to make up statutory performance requirements by the Atomic Energy Society of Japan (AESJ) and the Japan ...
2004-07-01
Energy Technology Data Exchange (ETDEWEB)
The operating histories and performance of a large (180 MWsub(e)) central condensing plant and five small (5 MWsub(e)) wellhead backpressure power plants are presented. The thermodynamic performance of the central plant is compared with an estimated possible performance based upon the work of Michaelides. Both types of plant have been shown to be reliable despite some problems due to the contaminants which are associated with geothermal steam.
1986-01-01
THE EFFECTS OF RESPONSE EFFORT ON SAFE PERFORMANCE BY THERAPISTS AT AN AUTISM TREATMENT FACILITY
UK PubMed Central (United Kingdom)
The effects of response effort on safe behaviors (i.e., glove wearing, hand sanitizing, and electrical outlet replacement) exhibited by therapists at an autism treatment center were examined. Participants...Full Text Available
2010-01-01
Study on the transient piping vibration of power plant. Secondary piping system of Wolsung 1 unit.
In order to maintain a safe operation and availability of generating facilities, qualitative and quantitative assessment of piping vibration was performed vibration sources and damages of piping support was identified on the second piping system of Wolsun...
1996-01-01
Mound Facility explosives incinerator
Energy Technology Data Exchange (ETDEWEB)
The design and performance of small incinerators used at the Mound Laboratory for the disposal of explosives are described. These units, which cost less than $1000 each, are about the size of a 55-gal drum, have water jackets for cooling, and have provided a flexible, efficient, and clean burning explosives disposal unit. (LCL)
1980-01-01
Hazard Evaluation and Technical Assistance Report No. TA 76-100, ASARCO, East Helena, Montana.
A Hazard Evaluation and Technical Assistance investigation was performed by NIOSH on February 1-4, 1977, at ASARCO, East Helena, Montana, a facility engaged in lead smelting. The survey was prompted by a request from the Regional OSHA Director in referenc...
1977-01-01
UK PubMed Central (United Kingdom)
BackgroundChina has had no effective and systematic information system to provide guidance for strengthening PHC (Primary Health Care) or account to citizens on progress. We report...Full Text Available
British Library Electronic Table of Contents (United Kingdom)
A dry interim storage facility has been constructed at the Wolsung power plant in Korea. This dry storage facility has seven separated modules. There are 40 long slender cylinders in one module. In one cylinder, ten baskets where sixty CANDU spent fuel bundles are loaded are stacked and stored. For this dry storage facility, analyses and tests for hypothetical accident conditions that might occur while moving and storing the baskets into a cylinder were performed. In a demonstration test, one of test basket models did not satisfy one of the safety-related requirements. Thus, the revised basket designs were generated using a structural evaluation based on finite element analyses and specimen tests. Among these revised designs, one design was chosen as a final revised basket design. The fina...
2011-01-01
CLOSURE OF THE FAST FLUX TEST FACILITY (FFTF) HISTORY & STATUS & FUTURE PLANS
Energy Technology Data Exchange (ETDEWEB)
In 1993, the US Department of Energy (DOE) decided to shut down the Fast Flux Test Facility (FFTF) due to lack of national missions that justified the annual operating budget of approximately $88M/year. The initial vision was to ''deactive'' the facility to an industrially and radiologically safe condition to allow long-term, minimal surveillance storage until approximately 2045. This approach would minimize near term cash flow and allow the radioactive decay of activated components. The final decontamination and decommissioning (D and D) would then be performed using then-current methodology in a safe and efficient manner. the philosophy has now changed to close coupling the initial deactivation with final D and D. This paper presents the status of the facility and focuses on the future challenge of sodium removal.
2006-02-24
Assessment of radiological safety of Wolsung site at site boundary considering crack impact
British Library Electronic Table of Contents (United Kingdom)
The number of spent fuel storage facilities in the world continues to increase because of "Wait and See" policies and delay of a permanent disposal plan. The temporary spent fuel storage concept is changing to a pre-disposal storage concept. Strengthened safety concepts are required for expanded spent fuel storage facilities and sites. The Korea Hydro and Nuclear Power Company is planning to construct a reinforced concrete MACSTOR-400 facility at Wolsung. In concrete dry spent fuel storage structures, cracks can occur due to radiant heat and environmental chloride. The likelihood of cracking increases over time. Research on changes in shielding performance from one collinear crack in the surface of a concrete facility has been carried out. However there is no research about public radiolog...
2010-01-01
Energy Technology Data Exchange (ETDEWEB)
Natural circulation experiments carried out in the REWET-III facility in 1985 have been used for RELAP5/MOD2 assessment. The REWET-III facility is a scaled-down model of VVER-440 type reactors. The facility consists of a pressure vessel in which the downcomer is simulated with an external pipe assembly, hot and cold legs with loop seals and a horizontal steam generator. The volume scaling factor compared to the reference reactor is 1:2333. The present paper summarizes the experiences gained in the RELAP5/MOD2 calculations of selected REWET-III single- and two-phase natural circulation experiments. The code's ability to represent the main phenomena of experiments in both cases was satisfactory.
1992-04-01
Energy Technology Data Exchange (ETDEWEB)
Natural circulation experiments carried out in the REWET-III facility in 1985 have been used for RELAP5/MOD2 assessment. The REWET-III facility is a scaled-down model of VVER-440 type reactors. The facility consists of a pressure vessel in which the downcomer is simulated with an external pipe assembly, hot and cold legs with loop seals and a horizontal steam generator. The volume scaling factor compared to the reference reactor is 1:2333. The present paper summarizes the experiences gained in the RELAP5/MOD2 calculations of selected REWET-III single- and two-phase natural circulation experiments. The code`s ability to represent the main phenomena of experiments in both cases was satisfactory.
1992-04-01
International Nuclear Information System (INIS)
Natural circulation experiments carried out in the REWET-III facility in 1985 have been used for RELAP5/MOD2 assessment. The REWET-III facility is a scaled-down model of VVER-440 type reactors. The facility consists of a pressure vessel in which the downcomer is simulated with an external pipe assembly, hot and cold legs with loop seals and a horizontal steam generator. The volume scaling factor compared to the reference reactor is 1:2333. The present paper summarizes the experiences gained in the RELAP5/MOD2 calculations of selected REWET-III single- and two-phase natural circulation experiments. The code's ability to represent the main phenomena of experiments in both cases was satisfactory.
1992-01-01
Applications and benefits of the FFTF IEM cell training facility
Energy Technology Data Exchange (ETDEWEB)
The Interim Examination and Maintenance (IEM) Cell is located within the Fast Flux Test Facility (FFTF) Reactor Containment Building. This cell is a complex vertical hot cell whose purpose is to process reactor experiments and to perform maintenance on reactor and refueling components. Because access to this very complex cell is limited, a mock-up called the IEM Training Facility (IEMTF) has been developed. The IEMTF provides the IEM cell with many valuable benefits. Four of these benefits are: (1) development of alternate processing methods; (2) hands-on evaluation of equipment problems; (3) a ready source of verified parts, and (4) training facilities for IEM Cell technicians.
1982-05-01
Development of high resolution imaging detectors for X-ray astronomy
Energy Technology Data Exchange (ETDEWEB)
High (spatial) resolution imaging detectors for X-ray astronomy were developed. Several prototype detectors built and their feasibility and baseline performance were assessed. Two of these detector types are proposed for investigations on the advanced X-ray astrophysics facility (AXAF). The readiness of a new X-ray imaging system, the charge coupled device (CCD) imaging specctrometer is outlined, and state of the art performance parameters for microchannel plate (MCP) and CCD detectors are measured. Laboratory facilities and procedures for coating MCP are developed general high resolution imagery systems are analyzed.
1985-03-01
Development of high resolution imaging detectors for X-ray astronomy
International Nuclear Information System (INIS)
High (spatial) resolution imaging detectors for X-ray astronomy were developed. Several prototype detectors built and their feasibility and baseline performance were assessed. Two of these detector types are proposed for investigations on the advanced X-ray astrophysics facility (AXAF). The readiness of a new X-ray imaging system, the charge coupled device (CCD) imaging specctrometer is outlined, and state of the art performance parameters for microchannel plate (MCP) and CCD detectors are measured. Laboratory facilities and procedures for coating MCP are developed general high resolution imagery systems are analyzed.
1985-01-01
Corrosion studies at the Wilsonville, Alabama, coal liquefaction facility during 1983
During 1983, Oak Ridge National Laboratory continued a study of materials performance at the Wilsonville, Alabama, Advanced Coal Liquefaction Research and Development Facility. Materials performance was evaluated by exposure and analysis of corrosion coupons and U-bend specimens, chemical analysis of related process streams, and ultrasonic determination of the thickness of walls of various components. The results of these studies are useful to current plant operators and to designers of future large-scale plants. 18 references, 4 figures, 12 tables.
1984-10-01
Structure of an accelerator island with one step on double period of conserving area mapping
International Nuclear Information System (INIS)
The structure of the P-2, S-1 accelerator mode with one step, S-1, on double period, P-2 for systems, described by the Harper mapping as well as by standard mapping, is analyzed. Detailed analysis of stability criteria is given and comparison with the results of numerical analysis is performed. Three-period compression of the P-2, S-1 island is revealed in the standard mapping. Refs. 7, figs. 7.
A study was made of the timber products processing point source category, for the purpose of developing information to assist the EPA in establishing effluent limitations guidelines and standards to implement sections 301, 304, 306, and 307 of the Federal Water Pollution Control Act Amendments of 1972. The document is the result of that study.
1974-08-01
Energy Technology Data Exchange (ETDEWEB)
The Savannah River Site disposes of low-level radioactive waste within on-site engineered disposal facilities. The Savannah River Site must demonstrate that these disposals meet the requirements of DOE Order 435 . 1 through a process known as performance assessment (PA). The objective of this document is to provide the radionuclide -specific data needed for the PA calculations . This work is part of an on-going program to periodically review and update existing PA work as new data becomes available. Revision of the E -Area Low-Level Waste Facility PA is currently underway. The number of radionuclides selected to undergo detailed analysis in the PA is determined by a screening process. The basis of this process is described. Radionuclide-specific data for half-lives, decay modes, daughters, dose conversion factors and groundwater concentration limits are presented with source references and methodologies.
2007-03-20
Energy Technology Data Exchange (ETDEWEB)
The Institute of Energetic and Nuclear Research - IPEN is a research and development institution, located in a densely populated area, in the city of Sao Paulo. The nuclear fuel cycle was developed from the Yellow Cake to the enrichment and reconversion at IPEN. After this phase, all the technology was transferred to private enterprises and to the Brazilian Navy (CTM/SP). Some plants of the fuel cycle were at semi-industrial level, with a production over 20 kg/h. As a research institute, IPEN accomplished its function of the fuel cycle, developing and transferring technology. With the necessity of space for the implementation of new projects, the uranium hexafluoride (UF{sub 6}) production plant was chosen, since it had been idle for many years and presented potential leaking risks, which could cause environmental aggression and serious accidents. This plant decommission required accurate planning, as this work had not been carried out in Brazil before, for this type of ...
2008-07-01
Routine environmental audit of the Y-12 Plant, Oak Ridge, Tennessee
Energy Technology Data Exchange (ETDEWEB)
This report documents the results of the routine environmental audit of the Oak Ridge Y-12 Plant (Y-12 Plant), Anderson County, Tennessee. During this audit, the activities conducted by the audit team included reviews of internal documents and reports from previous audits and assessments; interviews with U.S. Department of Energy (DOE), State of Tennessee regulatory, and contractor personnel; and inspections and observations of selected facilities and operations. The onsite portion of the audit was conducted August 22-September 2, 1994, by the DOE Office of Environmental Audit (EH-24), located within the Office of Environment, Safety and Health (EH). DOE 5482.1 B, {open_quotes}Environment, Safety, and Health Appraisal Program,{close_quotes} establishes the mission of EH-24 to provide comprehensive, independent oversight of DOE environmental programs on behalf of the Secretary of Energy. The ultimate goal of EH-24 is enhancement of environmental protection and ...
1994-09-01
Initiation of conformal radiotherapy with a multileaf-collimator - An approach to clinical routine
International Nuclear Information System (INIS)
The implementation of a three-dimensional conformal radiotherapy facility in the radiotherapy department of the Heinrich Heine University is described. Complex radiotherapy techniques with commercially available networked systems are introduced to improve clinical work. Over 18 month we have gained clinical experience with a PHILIPS Multileaf Collimator (MLC) mounted on a SL 25 linear accelerator. For a limited period the MLC was used as a conventional blocking device. The standard MLC-shapes are controlled with a stand-alone computer system. In addition, a three-dimensional treatment planning system (3-D-TPS / TMS-Radix, Helax AB) based on convolution/superposition algorithms was recently installed. Treatment optimization is achieved using static field arrangements with complete volumetric computerized tomographic patient data for 3-D-TPS. Conformal adaptation of the 95%-isodose to the Planning Target Volume (PTV, ICRU 50) results in ...
1995-10-01
Development of a neutron/. gamma. ray radiation monitor
Energy Technology Data Exchange (ETDEWEB)
Personnel radiation monitoring is essential to the operation of any nuclear facility and work in this area continues to strive for an accurate determination of personnel dose. In particular recent attention has been focused upon the need to improve the accuracy of neutron dosimetry, mainly because of their high Relative Biological Effectiveness. In this work the feasibility of using the NE-213 liquid scintillation detector as an efficient neutron/..gamma.. ray radiation monitor is demonstrated. Derivative method spectrum unfolding used in MATXUF for on-line analysis of fast neutron spectra has also been applied to real time ..gamma.. spectrum unfolding (MATXUF2), making possible simultaneous on-line monitoring of both fast neutrons and gammas. To eliminate the negative fluxes in the unfolded ..gamma.. spectra created by the photopeak-Compton edge combination in the plateau portion of the knee response, correcting equations using a linearized approximation to the ...
1983-01-01
Development of a neutron/#gamma# ray radiation monitor
International Nuclear Information System (INIS)
Personnel radiation monitoring is essential to the operation of any nuclear facility and work in this area continues to strive for an accurate determination of personnel dose. In particular recent attention has been focused upon the need to improve the accuracy of neutron dosimetry, mainly because of their high Relative Biological Effectiveness. In this work the feasibility of using the NE-213 liquid scintillation detector as an efficient neutron/#gamma# ray radiation monitor is demonstrated. Derivative method spectrum unfolding used in MATXUF for on-line analysis of fast neutron spectra has also been applied to real time #gamma# spectrum unfolding (MATXUF2), making possible simultaneous on-line monitoring of both fast neutrons and gammas. To eliminate the negative fluxes in the unfolded #gamma# spectra created by the photopeak-Compton edge combination in the plateau portion of the knee response, correcting equations using a linearized approximation to the electron ...
1983-01-01
Development of a Neutron/gamma Ray Radiation Monitor.
Personnel radiation monitoring is essential to the operation of any nuclear facility and work in this area continues to strive for an accurate determination of personnel dose. In particular recent attention has been focused upon the need to improve the accuracy of neutron dosimetry, mainly because of their high Relative Biological Effectiveness. In this work the feasibility of using the NE-213 liquid scintillation detector as an efficient neutron/gamma ray radiation monitor is demonstrated. Derivative method spectrum unfolding used in MATXUF for on-line analysis of fast neutron spectra has also been applied to real time gamma spectrum unfolding (MATXUF2), making possible simultaneous on-line monitoring of both fast neutrons and gammas. To eliminate the negative fluxes in the unfolded gamma spectra created by the photopeak-compton edge combination in the plateau portion of the knee response, correcting equations using a linearized approximation to the electron ...
1983-01-01
Performance assessment overview for subseabed disposal of high level radioactive waste
Energy Technology Data Exchange (ETDEWEB)
The Subseabed Disposal Project (SDP) was part of an international program that investigated the feasibility of high-level radioactive waste disposal in the deep ocean sediments. This report briefly describes the seven-step iterative performance assessment procedures used in this study and presents representative results of the last iteration. The results of the performance are compared to interim standards developed for the SDP, to other conceptual repositories, and to related metrics. The attributes, limitations, uncertainties, and remaining tasks in the SDP feasibility phase are discussed.
1997-06-01
The HIPAA privacy rule (HIPAA) has had both positive and negative effects on the release of patient information by healthcare facilities. Although the intention of HIPAA was to protect patient privacy and to promote security and confidentiality of patient information, it has had unintended consequences for facilities. To identify some of these unintended effects, two expert panels of health information management directors from healthcare facilities participated in the nominal group technique meetings. They identified 70 barriers related to release of patient information associated with the implementation of HIPAA. The perceived biggest barriers were increases in the public's misunderstanding about release of patient information, lack of an umbrella policy or regulation defining infractions and enforcement that allows individual institutions to make their own interpretations, and challenges to health information management ...
2007-03-23
The role of autonomic neuropathy in diabetic foot ulceration.
UK PubMed Central (United Kingdom)
Five standard, non-invasive tests of cardiovascular, autonomic function were performed in each of four groups of 30 subjects: controls, group 1, diabetics without clinical evidence of neuropathy; group...Full Text Available
1986-09-01
UK PubMed Central (United Kingdom)
IntroductionRecent Food and Drug Administration legislation enables the mandating of product performance standards for cigarette smoke and the evaluation of manufacturers’...Full Text Available
2009-12-01
Flue gas desulfurization: scrubber types and selection criteria
Economic and performance criteria that should be used in the selection of a scrubber system are presented. Selection should be based on the type of emissions put out by a plant and the removal efficiency required by pollution control standards. Costs and efficiencies for 10 different scrubber systems are reported. (10 diagrams)
1980-05-01
This document presents regulations and research support the EPA`s effluent limitations for the paving and roofing materials point source category.
1974-12-01
...8Eligibility Criteria: Emotional/Behavioral Disorders Guidance for Paragraph...at-risk for emotional/behavioral disorders and their parents to help...Evaluation Team for Emotional/behavioral Disorders: Psychologist,...
2010-10-01
The Minimal Scale Invariant Extension of the Standard Model
We perform a systematic analysis of an extension of the Standard Model that includes a complex singlet scalar field and is scale invariant at the tree level. We call such a model the Minimal Scale Invariant extension of the Standard Model (MSISM). The tree-level scale invariance of the model is explicitly broken by quantum corrections, which can trigger electroweak symmetry breaking and potentially provide a mechanism for solving the gauge hierarchy problem. Even though the scale invariant Standard Model is not a realistic scenario, the addition of a complex singlet scalar field may result in a perturbative and phenomenologically viable theory. We present a complete classification of the flat directions which may occur in the classical scalar potential of the MSISM. After calculating the one-loop effective potential of the MSISM, we investigate a number of representative scenarios and determine their ...
2010-01-01
Recommendations for a proposed standard for performing systems analysis
In August 1995, the Nuclear Regulatory Commission (NRC) issued a policy statement proposing improved regulatory decisionmaking by increasing the use of PRA [probabilistic risk assessment] in all regulatory matters to the extent supported by the state-of-the-art in PRA methods and data. A key aspect in using PRA in risk-informed regulatory activities is establishing the appropriate scope and attributes of the PRA. In this regard, ASME decided to develop a consensus PRA Standard. The objective is to develop a PRA Standard such that the technical quality of nuclear plant PRAs will be sufficient to support risk-informed regulatory applications. This paper presents examples recommendations for the systems analysis element of a PRA for incorporation into the ASME PRA Standard.
1998-08-01
Recommendations for a proposed standard for performing systems analysis
Energy Technology Data Exchange (ETDEWEB)
In August 1995, the US Nuclear Regulatory Commission (NRC) issued a policy statement proposing improved regulatory decision making by increasing the use of probabilistic risk assessment (PRA) in all regulatory matters to the extent supported by the state-of-the-art in PRA methods and data. A key aspect in using PRA in risk-informed regulatory activities is establishing the appropriate scope and attributes of the PRA. In this regard, the American Society of Mechanical Engineers (ASME) decided to develop a consensus PRA standard. The objective is to develop a PRA standard such that the technical quality of nuclear plant PRAs will be sufficient to support risk-informed regulatory applications. The authors present example recommendations for the systems analysis element of a PRA for incorporation into the ASME PRA standard.
1998-12-31
Benchmarking of refinery emissions performance : Executive summary
International Nuclear Information System (INIS)
This study was undertaken to collect emissions performance data for Canadian and comparable American refineries. The objective was to examine parameters that affect refinery air emissions performance and develop methods or correlations to normalize emissions performance. Another objective was to correlate and compare the performance of Canadian refineries to comparable American refineries. For the purpose of this study, benchmarking involved the determination of levels of emission performance that are being achieved for generic groups of facilities. A total of 20 facilities were included in the benchmarking analysis, and 74 American refinery emission correlations were developed. The recommended benchmarks, and the application of those correlations for comparison between Canadian and American refinery performance, were ...
2003-01-01
This report provides test results on the thermal performance of an Owens-Illinois Sunpak liquid, evacuated tube, solar collector under simulated conditions. The test was conducted using the Marshall Space Flight Center Solar Simulator in accordance with the test requirements specified in ASHRAE 93-77 (Method of Testing to Determine the Thermal Performance of Solar Collectors) and the procedures contained in MTCP-FA-SHAC-400 (Procedure for Operation of the MSFC Solar Simulator Facility). The tests were performed on a module used on the early demonstration projects. A current production module is undergoing tests with results to be in a subsequent report.
1979-10-10
International Nuclear Information System (INIS)
As part of the general QC/QA management of the k_0-standardization, three types of 'SMELS' (synthetic multi-element standards) are being developed to check the performance of k_0-NAA when implemented in a laboratory. Phenol-formaldehyde resin is proposed in this paper as the matrix of choice. Based on previous work, this material could be prepared with sufficient purity so as to make interferences with the spiking elements negligible. The matrix was found to be adequately resistant towards high neutron flux irradiation. A selection was made of compounds, soluble in ethyl alcohol, for spiking the prepolymer ethanolic solution with the elements of interest. Finally, some prototypes were prepared and a satisfactory homogeneity of the spiked elements was found for 50 mg sample intake.
2001-07-12
Development of American National Standard on External Event PRA Methodology
International Nuclear Information System (INIS)
During the last ten years, the U.S. Nuclear Regulatory Commission and the U.S. nuclear utilities have been developing methods and requirements for risk-informed applications making use of probabilistic risk assessments (PRA) of nuclear power plants. Early in this process, it became clear that the existing PRAs were done with different objectives and methodologies by different analysts. For uniformity and consistency in future risk-informed applications, industry consensus standards on probabilistic risk assessments were deemed to be essential. Currently, the following standards have been published or under preparation: - ASME RA-S-2002: 'Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications', Addendum C, March 2005. - ANSI/ANS-58.21-2003 'External-Events PRA Methodology' March 2003. - ANS-58.22 'Low Power and Shutdown PRA Standard'. - ANS-58.23 'Fire PRA Methodology ...
2007-11-14
Improving system modeling accuracy with Monte Carlo codes
International Nuclear Information System (INIS)
The use of computer codes based on Monte Carlo methods to perform criticality calculations has become common-place. Although results frequently published in the literature report calculated k_e_f_f values to four decimal places, people who use the codes in their everyday work say that they only believe the first two decimal places of any result. The lack of confidence in the computed k_e_f_f values may be due to the tendency of the reported standard deviation to underestimate errors associated with the Monte Carlo process. The standard deviation as reported by the codes is the standard deviation of the mean of the k_e_f_f values for individual generations in the computer simulation, not the standard deviation of the computed k_e_f_f value compared with the physical system. A more subtle problem with the standard deviation of the mean as reported by the codes is ...
1996-06-16
International Nuclear Information System (INIS)
Radiological and environmental protection experience associated with the reactor cover gas processing system at the Fast Flux Test Facility (FFTF) has been excellent. Personnel radiation exposures received from operating and maintaining the reactor cover gas processing system have been very low, the system has remained free of radioactive particulate contamination through the first seven operating cycles (cesium contamination was detected at the end of Cycle 8A), and releases of radioactivity to the environment have been very low, well below environmental standards. This report discusses these three aspects of fast reactor cover gas purification over the first eight operating cycles of the FFTF (a duration of a little more than four years, from April 1982 through July 1986).
1986-09-24
FDS3 simulations of indoor hydrocarbon fires engulfing radioactive waste packages
International Nuclear Information System (INIS)
The thermal environment of a hypothetical large indoor hydrocarbon pool fire is more complex compared to outdoor fires and can be more severe for engulfed objects. In order to analyze potential thermal environments for interim storage of spent fuel casks or low-level radioactive waste packages engulfed in pool fires numerical simulations with the CFD fire code FDS3 were carried out for different storage configurations. In addition, data of indoor pool fire experiments were used to validate the model for this type of application. A series of pool fire experiments under different ventilation conditions and varied pool surface (1 m"2 - 4 m"2) inside a compartment of 3.6 m x 3.6 m x 5.7 m was conducted at iBMB (Institut fuer Baustoffe, Massivbau und Brandschutz) of Braunschweig University of Technology, Germany. The instrumentation included thermocouples, heatflux and pressure gauges, bi-directional flow probes and gas concentration measurements. A mock low-level waste drum equipped with ...
2004-09-20
Energy Technology Data Exchange (ETDEWEB)
This paper reports on current dual fuel engines utilizing standard mechanical (Bosch type) fuel injection systems set to 5--6 percent pilot delivery that do not appear capable of reducing NO{sub x} emissions much below the current minimum of 4 g/bhp-h without incurring substantial penalties in efficiency and operability. A prototype Electronic Pilot Fuel Injector (EPFI) was designed that overcomes the shortcomings of the mechanical injection system, consistently delivering 3 percent or less pilot at pressures as high as 20,000 psi. The EPFI was installed and tested in one cylinder of a standard production dual fuel engine operating at a waste water treatment facility.
1990-07-01
Environmental surveillance at Hanford for CY-1979
Energy Technology Data Exchange (ETDEWEB)
Environmental data were collected for most environmental media including air, Columbia River water, external radiation, foodstuffs (milk, beef, eggs, poultry, and produce) and wildlife (deer, fish, and game birds), as well as soil and vegetation samples. In general, offsite levels of radionuclides attributable to Hanford operations during 1979 were indistinguishable from background levels. The data are summarized in the following highlights. Air quality measurements of NO/sub 2/ in the vicinity of the Hanford Site and releases of SO/sub 2/ onsite were well within the applicable federal and state standards. Particulate air concentrations exceed the standards primarily because of agricultural activities in the area. Discharges of waste water from Hanford facilities in the Columbia River under the National Pollution Discharge Elimination System (NPDES) permit were all within the parameter limits on the permit.
1980-04-01
This environmental assessment quantifies the water quality-related benefits for Transportation Equipment Cleaning (TEC) facilities based on site-specific analyses of current conditions and the conditions that would be achieved by process changes under proposed BAT (Best Available Technology) and PSES (Pretreatment Standards for Existing Sources) controls. The US Environmental Protection Agency (EPA) estimated instream pollutant concentrations for 157 priority and nonconventional pollutants from three subcategories (barge-chemical and petroleum, rail-chemical, and truck-chemical) of direct and indirect discharges using stream dilution modeling. The potential impacts and benefits to aquatic life are projected by comparing the modeled instream pollutant concentrations to published EPA aquatic life criteria guidance or to toxic effect levels.
1998-05-01
SSHS - Departments - Taught Courses - Undergraduate Prospectus - Loughborough University
... Indoor facilities include a 50 metre swimming pool, various sports halls, a netball and badminton centre, a dance studio, a high performance athletics centre, the ECB National Cricket Academy, and the National Gymnastics Performance and Research Centre, whilst outdoors there are floodlit all-weather areas, a water-based ...
Performance testing of the FMC Fresnel-Belt Concentrating Solar Collector
Energy Technology Data Exchange (ETDEWEB)
The results of tests performed on the FMC Fresnel-Belt Solar Collector at the Midtemperature Solar Systems Test Facility are summarized. Tests were conducted over a temperature range from 100 to 250/sup 0/C. Test objectives are defined, test procedures are described, and test results and conclusions are given.
1980-01-01
Fast reactor fuel pin performance requirements for off-normal events
International Nuclear Information System (INIS)
HEDL is conducting an experimental transient testing program to evaluate the performance of prototypic Fast Flux Test Facility (FFTF) fuel pins up to the cladding integrity limit. The relationship is described of the HEDL/TREAT transient overpower test program to the confirmation of FFTF fuel pin design bases via the FFTF fuel pin design procedure.
Waste sampling and characterization facility (WSCF) maintenance implementation plan
Energy Technology Data Exchange (ETDEWEB)
This Maintenance Implementation Plan (MIP) is written to satisfy the requirements of the US Department of Energy (DOE) Order 4330.4B, Maintenance Management Program that specifies the general policy and objectives for the establishment of the DOE controlled maintenance programs. These programs provide for the management and performance of cost effective maintenance and repair of the DOE property, which includes facilities. This document outlines maintenance activities associated with the facilities operated by Waste Management Hanford, Inc. (WMH). The objective of this MIP is to provide baseline information for the control and execution of WMH Facility Maintenance activities relative to the requirements of Order 4330.4B, assessment of the WMH maintenance programs, and actions necessary to maintain compliance with the Order. Section 2.0 summarizes the history, mission and description of the WMH ...
1997-08-13
Waste sampling and characterization facility (WSCF)
Energy Technology Data Exchange (ETDEWEB)
The Waste Sampling and Characterization Facility (WSCF) complex consists of the main structure (WSCF) and four support structures located in the 600 Area of the Hanford site east of the 200 West area and south of the Hanford Meterology Station. WSCF is to be used for low level sample analysis, less than 2 mRem. The Laboratory features state-of-the-art analytical and low level radiological counting equipment for gaseous, soil, and liquid sample analysis. In particular, this facility is to be used to perform Resource Conservation and Recovery Act (RCRA) of 1976 and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 sample analysis in accordance with U.S. Environmental Protection Agency Protocols, room air and stack monitoring sample analysis, waste water treatment process support, and contractor laboratory quality assurance checks. The samples to be analyzed contain very low concentrations ...
1994-10-01
Energy Technology Data Exchange (ETDEWEB)
The third regular inspection of No.2 plant in Sendai Nuclear Power Station was carried out from December 27, 1988 to May 25, 1989. The parallel operation was resumed on April 28, 1989, 123 days after the parallel off. The facilities which were the object of inspection were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment installation and emergency electric power generation system. On the facilities which were the object of inspection, the appearance, disassembling, leak, function, performance and other inspections were carried out. As the results, significant in indication was observed in 8 bolts for fixing the flow-changing vanes of primary coolant pumps, and broken valve spindles were found, but other abnormality was not found. The works related to ...
1990-03-01
International Nuclear Information System (INIS)
The second regular inspection of No.2 plant in Sendai Nuclear Power Station was carried out from October 5, 1987 to January 8, 1988. the parallel operation was resumed on December 8, 1987, 65 days after the parallel off. The facilities as the object of inspection were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment installation, and emergency power generation system. On these facilities as the object of inspection, the appearance, disassembling, leak, function, performance and other inspections were carried out, and abnormality was not found at all. The works related to this regular inspection were accomplished within the range of allowable dose based on the relevant laws. The main reconstruction works carried out during the period of this regular ...
1988-01-01
Energy Technology Data Exchange (ETDEWEB)
The second regular inspection of No.2 plant in Sendai Nuclear Power Station was carried out from October 5, 1987 to January 8, 1988. the parallel operation was resumed on December 8, 1987, 65 days after the parallel off. The facilities as the object of inspection were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment installation, and emergency power generation system. On these facilities as the object of inspection, the appearance, disassembling, leak, function, performance and other inspections were carried out, and abnormality was not found at all. The works related to this regular inspection were accomplished within the range of allowable dose based on the relevant laws. The main reconstruction works carried out during the period of this regular ...
1988-08-01
A combined cycle engine test facility
Energy Technology Data Exchange (ETDEWEB)
Rocket-Based Combined-Cycle (RBCC) engines intended for missiles and/or space launch applications incorporate features of rocket propulsion systems operating in concert with airbreathing engine cycles. Performance evaluation of these types of engines, which are intended to operate from static sea level take-off to supersonic cruise or accerlerate to orbit, requires ground test capabilities which integrate rocket component testing with airbreathing engine testing. A combined cycle engine test facility has been constructed in the General Applied Science Laboratories, Inc. (GASL) Aeropropulsion Test Laboratory to meet this requirement. The facility was designed to support the development of an innovative combined cycle engine concept which features a rocket based ramjet combustor. The test requirements included the ability to conduct tests in which the propulsive force was generated by rocket only, the ramjet only and ...
1995-09-01
Radionuclide Air Emissions Report for the Hanford Site Calendar year 1998
Energy Technology Data Exchange (ETDEWEB)
This report documents radionuclide air emissions from the Hanford Site in I998 and the resulting effective dose equivalent to the maximally exposed individual (MEI) member of the public. The report has been prepared in accordance with the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (40 CFR SI), Subpart H, ''National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities,'' and with the Washington Administrative Code Chapter 246-247, Radiation Protection--Air Emissions. The federal regulations in 40 CFR 61, Subpart H; require the measurement and reporting of radionuclides emitted from Department of Energy facilities and the resulting offsite dose from those emissions. A standard of 10 mrem/yr effective dose ...
1999-06-15
International Nuclear Information System (INIS)
National Nuclear Safety Department is authorized by Infra (Iranian Nuclear Regulatory Authority) for issuing rules and regulation and conducting the licensing and supervisory process for nuclear facilities. The main responsibilities of the NNSD are conducted via five main division are, nuclear codes and standards, Nuclear Safety assessment, Authorization, Inspection and Enforcement and Technical Support. In this paper, the functions and responsibilities of TSD in enhancing nuclear safety are described. Examples of main tasks to support the Nuclear Safety assessment division regarding to technical calculations and research of safety issues in licensing documents are provided. (author)
2007-08-01
Requirements and guidelines for NSLS experimental beam line vacuum systems: Revision A
Energy Technology Data Exchange (ETDEWEB)
Requirements are provided for NSLS beam line front ends and vacuum interlocks. Guidelines are provided for UHV beam line vacuum systems, including materials, vacuum hardware (pumps, valves, and flanges), acoustic delay lines and beam line fast valves, instrumentation, fabrication and testing, and the NSLS cleaning facility. Also discussed are the design review for experimenters' equipment that would be connected to the NSLS and acceptance tests for any beam line to be connected with the ring vacuum. Also appended are a description of the acoustic delay line as well as the NSLS vacuum standards and NSLS procedures. (LEW)
1986-10-01
Neutron radiography with the cyclotron, 5
International Nuclear Information System (INIS)
Reliable facility of cyclotron-based real time neutron radiography system has been developed and applied to some industrial components. The equipment for neutron fluoroscopy is based on a sub-compact cyclotron and a LiF/ZnS (Ag) fluorescent screen viewed by a silicon intensifier target TV camera. The real time image is monitored on a CRT, recorded with a standard video recorder and processed by a digital image processor. The effectiveness of our real time neutron radiograph has been demonstrated to be applicable to not only the dynamic observation but also the magnifying and stereoscopic observation of fluoroscopic images. (author).
1987-01-01
Less BOP running with variable bore rams
Energy Technology Data Exchange (ETDEWEB)
The marine ram-type blowout preventer deployed from an offshore drilling rig has one serious disadvantage, its inaccessibility. A development to promote reliability of the subsea ram-type preventer and reduce the excess running and pulling to charge out rams, is the variable bare ram (VBR). Unlike the standard ram, the VBR has the ability to pack off a range of pipe sizes. Interest in VBR's has been revived and research and development in this equipment goes on at each of three manufacturer's facilities in Houston.
1984-04-01
High voltage transmission lines - what are the hazards
International Nuclear Information System (INIS)
With the increasing use of high voltage alternating current (HVAC) transmission lines there is a growing concern among the public about possible human health effects resulting from exposure to the electric fields associated with these lines. While there is no definitive evidence of such effects, mounting public fear and activism over hypothesized health risks is already causing delays in the licensing and constuction of major power transmission facilities, and is encouraging the formation of regulatory policy. This paper briefly reviews the concerns, biological effects data and standards for HVAC transmission lines.
1984-07-01
First results from the Lund NMP particle detector system
International Nuclear Information System (INIS)
The design and first results from a Double Sided Silicon Strip Detector (DSSSD) recently installed at the Lund Nuclear Microprobe facility (NMP) are presented. The detector has 64 sector strips and 32 ring strips, which in combination give more than 2000 detector cells, each with characteristics comparable with a standard surface barrier detector (SBD). The detector has been tested both with radioactive sources and with different ion beams and energies. The most striking features are the high rate virtually pile-up free operation and also the possibility of detailed measurement of angular distributions.
2009-06-15
First results from the Lund NMP particle detector system
British Library Electronic Table of Contents (United Kingdom)
The design and first results from a Double Sided Silicon Strip Detector (DSSSD) recently installed at the Lund Nuclear Microprobe facility (NMP) are presented. The detector has 64 sector strips and 32 ring strips, which in combination give more than 2000 detector cells, each with characteristics comparable with a standard surface barrier detector (SBD). The detector has been tested both with radioactive sources and with different ion beams and energies. The most striking features are the high rate virtually pile-up free operation and also the possibility of detailed measurement of angular distributions.
2009-01-01
Annual Report 2007. Nuclear Regulatory Authority
International Nuclear Information System (INIS)
The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across tree parts and seven annexes the activities developed by the organism during 2007. The main topic are: the organization and the activity of the ARN; the regulatory standards; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the occupational surveillance; the environmental monitoring; improved organizational. Also, this publication have annexes with the following content: regulatory documents; inspections to medical, industrial and training installations; regulatory guides; measurement and evaluation of the drinking water of Ezeiza.
2004-07-11
Decommissioning of U.S. uranium production facilities
Energy Technology Data Exchange (ETDEWEB)
From 1980 to 1993, the domestic production of uranium declined from almost 44 million pounds U{sub 3}O{sub 8} to about 3 million pounds. This retrenchment of the U.S. uranium industry resulted in the permanent closing of many uranium-producing facilities. Current low uranium prices, excess world supply, and low expectations for future uranium demand indicate that it is unlikely existing plants will be reopened. Because of this situation, these facilities eventually will have to be decommissioned. The Uranium Mill Tailings and Radiation Control Act of 1978 (UMTRCA) vests the U.S. Environmental Protection Agency (EPA) with overall responsibility for establishing environmental standards for decommissioning of uranium production facilities. UMTRCA also gave the U.S. Nuclear Regulatory Commission (NRC) the responsibility for licensing and regulating uranium production and related activities, including ...
1995-02-01
Energy Technology Data Exchange (ETDEWEB)
A summary of the 1983 Critical Solvent Deashing unit performance at the Wilsonville Advanced Coal Liquefaction R and D Facility is presented. All periods of on feed operation, unscheduled shutdowns, and scheduled shutdowns are accounted for and tabulated. Causes of unscheduled shutdowns are identified and discussed. Details of repeated, major maintenance problems with various pieces of equipment are presented. Where applicable, solutions are discussed. Historical operations and maintenance data are presented and used for comparison purposes in order to better indicate areas of improvement in the unit. 4 references, 7 figures, 3 tables.
1985-03-01
International Nuclear Information System (INIS)
The system which is performed the transportation and measurement of drum automatically to measure the surface dose-rate of radioactive waste drum and can inspect place of contaminated sources and precise dose-rate within a drum according to measuring many places equally at the same time has been developed. It is expected that the system be used to minimized radiation exposure of workers and manage the drum effectively according to established at the production facilities as well as the radioactive waste treatment facilities. (author). 7 refs., 9 tabs., 16 figs.
The ANL X6B beamline at NSLS: A versatile facility
Energy Technology Data Exchange (ETDEWEB)
We have described the x-ray optics and beamline performance of the ANL X6B beam line at the NSLS. Considerable flexibility has been built into the beam line to accommodate a wide range of x-ray diffraction, scattering, and spectroscopy experiments with various requirements. We presented selected examples of experimental results and showed that with the high intensity, high energy resolution, high-q resolution, and energy tunability, the X6B beam line has become a versatile facility.
1994-07-01
Testing of the 1-MWth bench-model cavity-receiver steam generator
A schematic of the Bench cavity receiver system is given, and the primary objectives, schedule and research plan for each of four tests are discussed. The tests are: (1) cold flow testing to functionally check all valves and their response using high pressure nitrogen gas; (2) a hot checkout to simulate both steady state and transient flux inputs to the receiver which are expected at the French facility; (3) basic performance using solar energy at the French facility; and (4) ir radiant heat testing. (LEW)
Performance of rubber heat-stable and radiation-stable seals in helium coolant lines
International Nuclear Information System (INIS)
The integrity of helium circulation loop flanged joints has been attracting recent attention as a design problem, in the development of high-temperature facilities incorporating helium loops (e.g., the VRG-50 pilot nuclear facility). Elevated temperatures and pressures, and the radiation environment, impose additional requirements on sealant materials. This applies first and foremost to rubber seals, which have found widespread favor on account of its excellent elasticity, its ability to spontaneously conform to possible changes in the clearance in the seal assembly, and the low compressive stresses developed in the flange joint assembly.
Forthcoming (n, #gamma#) measurements on the Fe and Ni isotopes at CERN n_TOF
International Nuclear Information System (INIS)
An overview of the past, present and future research activities at the CERN neutron time of flight facility n_TOF is given, with special focus on the astrophysical aspects. During the first campaign (Phase I), neutron capture cross sections of relevance for several aspects of the s-process nucleosynthesis have been measured. A second campaign has recently started (Phase II), aiming at the study of the weak s-process component via accurate (n,#gamma#) measurements of the Fe and Ni isotopes. Some changes in the facility will allow us to perform these measurements with improved experimental conditions.
2010-01-01
Estimating the tritiated hydrocarbon decontamination factor by heavy methane
International Nuclear Information System (INIS)
As part of the start up of Los Alamos National Laboratory's new tritium-handling facility, the efficiency of a catalytic oxidation tritium decontamination system was investigated using deuterated methane. The tests were performed during the start up of the facility to confirm the operability of the system before introducing tritium and to provide a baseline for comparison. Techniques and instruments normally used for atmospheric tracer experiments using deuterated methane were applied virtually without modification. The sensitivity of this method allowed preliminary checks at the sub-ppm (v/v) level.
Conceptual design of a nuclear reactor facility for medical and biological purposes
Energy Technology Data Exchange (ETDEWEB)
Optimal neutron energy for boron neutron capture therapy (BNCT) has been studied. Epithermal neutron is superior to thermal neutrons in treating deep-seated tumors. Design of the epithermal neutron column for BNCT has been performed by using a two-dimensional transport calculation code. Aluminum and heavy water are used as moderation materials. A thermal neutron column is also designed using heavy water as thermalization material. The configuration of the facility for treatment and research of BNCT and also for basic radio-biological studies of neutrons has been presented.
1981-09-01
Conceptual design of a nuclear reactor facility for medical and biological purposes
International Nuclear Information System (INIS)
Optimal neutron energy for boron neutron capture therapy (BNCT) has been studied. Epithermal neutron is superior to thermal neutrons in treating deep-seated tumors. Design of the epithermal neutron column for BNCT has been performed by using a two-dimensional transport calculation code. Aluminum and heavy water are used as moderation materials. A thermal neutron column is also designed using heavy water as thermalization material. The configuration of the facility for treatment and research of BNCT and also for basic radio-biological studies of neutrons has been presented. (author).
Bechtel Hanford Inc. Network Security Plan for the EnvironmentalRestoration Contract
'As part of the Computer Protection Plan, this Network Security Plan identifies the specific security measures used to protect Bechtel Hanford, Inc.'s (BHI's) enterprise network. The network consists of the communication infrastructure and information systems used by BHI to perform work related to the Environmental Restoration Contract (ERC) at the Hanford Site. It provides electronic communication between the ERC-leased facilities in Richland, Washington, and facilities located on the Hanford Site. Network gateways to other site and offsite networks provide electronic communication with the remainder of the Hanford community.'
1999-06-30
Analysis of tritium mission FMEF/FAA fuel handling accidents
Energy Technology Data Exchange (ETDEWEB)
The Fuels Material Examination Facility/Fuel Assembly Area is proposed to be used for fabrication of mixed oxide fuel to support the Fast Flux Test Facility (FFTF) tritium/medical isotope mission. The plutonium isotope mix for the new mission is different than that analyzed in the FMEF safety analysis report. A reanalysis was performed of three representative accidents for the revised plutonium mix to determine the impact on the safety analysis. Current versions computer codes and meterology data files were used for the analysis. The revised accidents were a criticality, an explosion in a glovebox, and a tornado. The analysis concluded that risk guidelines were met with the revised plutonium mix.
1997-11-18
Energy Technology Data Exchange (ETDEWEB)
A thermohydraulic study of MTR fuel element is presented as a basic requirement for the development of an irradiation facility for testing fuel elements. A computer code named 'Thermo' has been developed for this purpose, which can stimulate different working conditions, such as, cooling, power elements and neutron flux, performing all pertinent thermohydraulic calculations. Thermocouples were used to measure the temperature gradients of the cooling fluid throughout the IEAR-1 reactor core. All experimental data are in good agreement with the theoretical model applied in this work. Finally, a draft of the proposed facility and its safety system is presented. (author)
1980-07-01
The {sup 234}U neutron capture cross section measurement at the n TOF facility
Energy Technology Data Exchange (ETDEWEB)
The neutron capture cross-section of {sup 234}U has been measured for energies from thermal up to the keV region in the neutron time-of-flight facility n-TOF, based on a spallation source located at CERN. A 4{pi} BaF{sub 2} array composed of 40 crystals, placed at a distance of 184.9 m from the neutron source, was employed as a total absorption calorimeter (TAC) for detection of the prompt {gamma}-ray cascade from capture events in the sample. This text describes the experimental setup, all necessary steps followed during the data analysis procedure. Results are presented in the form of R-matrix resonance parameters from fits with the SAMMY code and compared to the evaluated data of Endf in the relevant energy region, indicating the good performance of the n-TOF facility and the TAC. (authors)
2008-07-01
The status of the alpha-project
International Nuclear Information System (INIS)
A review of the ALPHA project is presented, including a summary of progress and current status. The project comprises the experimental and analytical investigation of the long-term decay heat removal phenomena from the containment of the next generation of ''passive'' Advanced Light Water Reactors. The effects of aerosols that may result from hypothetical severe accidents are also considered. The construction of the major ALPHA experimental facilities, PANDA, LINX-2 and AIDA, has been completed. First steady-state tests have been performed on PANDA. The other facilities are now in their commissioning phases. Scaling studies have guided the design of the experimental facilities. Several small-scale experimental and studies have already produced valuable results which can be used to direct the experimental work, as well as the design of the passive ALWRs. (author). 23 refs, 6 figs.
1996-04-01
The PANDA tests for SBWR certification
International Nuclear Information System (INIS)
The ALPHA project is centered around the experimental and analytical investigation of the long-term decay heat removal from the containments of the next generation of open-quotes passiveclose quotes ALWRs. The project includes integral system tests in the large-scale (1:25 in volume) PANDA facility as well as several other series of tests and supporting analytical work. The first series of experiments to be conducted in PANDA have become a required experimental element in the certification process for the General Electric Simplified Boiling Water Reactor (SBWR). The PANDA general experimental philosophy, facility design, scaling, and instrumentation are described. Steady-state PCCS condenser performance tests and extensive facility characterization tests were already conducted. The transient system behavior tests are underway; preliminary results from the first transient test M3 are reviewed.
1996-03-01
Energy Technology Data Exchange (ETDEWEB)
This report describes the status of nuclear safety and radiation protection in the facilities of the AREVA group and gives information on radiation protection in the service operations, as observed through the inspection programs and analyses carried out by the General Inspectorate in 2007. Having been submitted to the group's Supervisory Board, this report is sent to the bodies representing the personnel. Content: 1 - A look back at 2007 by the AREVA General Inspector: Visible progress in 2007, Implementation of the Nuclear Safety Charter, Notable events; 2 - Status of nuclear safety and radiation protection in the nuclear facilities and service operations: Personnel radiation protection, Event tracking, Service operations, Criticality control, Radioactive waste and effluent management; 3 - Performance improvement actions; 4 - Description of the General Inspectorate; 5 - Glossary.
2007-07-01
Reference equilibrium core with central flux irradiation facility for Pakistan research reactor-1
International Nuclear Information System (INIS)
In order to assess various core parameters a reference equilibrium core with Low Enriched Uranium (LEU) fuel for Pakistan Research Reactor (PARR-1) was assembled. Due to increased volume of reference core, the average neutron flux reduced as compared to the first higher power operation. To get a higher neutron flux an irradiation facility was created in centre of the reference equilibrium core where the advantage of the neutron flux peaking was taken. Various low power experiments were performed in order to evaluate control rods worth and neutron flux mapping inside the core. The neutron flux inside the central irradiation facility almost doubled. With this arrangement reactor operation time was cut down from 72 hours to 48 hours for the production of the required specific radioactivity. (author)
2008-07-01
Energy Technology Data Exchange (ETDEWEB)
This study characterized selected commercial volume reduction technologies as to performance and associated costs. VR facility designs were developed for each of the reference VR technologies. Associated on-site storage requirements and cost were also determined. Eight VR technologies were selected for consideration: improved compactor; high pressure compactor (supercompactor); incinerator; fluid bed dryer and incinerator; evaporator crystallizer; evaporator extruder; mobile incinerator; and mobile thin-film evaporator. A representative facility design was developed for each VR technology and for several combinations of technologies. Thirteen separate cases are noted in the following table when retrofit and new facilities are considered.
1984-11-01
Coal-liquefaction-process research quarterly report, January 1 - March 31, 1982
Objectives of the program are to understand the mechanisms of coal liquefaction, to determine the role of catalysts in the direct conversion of coal to liquids, to determine the mechanism of catalyst deactivation and to explore slurry phase catalyst systems. Specific projects include: short-contact time coal liquefaction, mineral matter effects and catalyst studies. During this period, work was performed on: (1) the stability, at reaction temperature, of a recycle solvent obtained from the Lummus Two Stage Liquefaction facility, (2) reactions of preasphaltenes and asphaltenes prepared under various reaction severities, (3) the evaluation of the catalyst level detector installed at the H-Coal facility, (4) the characterization of oil soluble metal compounds with respect to hydrogenation activity, and (5) characterization, deactivation and regeneration of catalysts obtained from both the H-Coal and Lummus ...
1982-10-01
The Challenge Ahead for Rural Schools.
Describes general trends in the quality of rural education: equivalent rural and urban performance on national standardized tests and high school graduation rates but continuing rural deficits in college attendance and teacher qualifications. Discusses the below-average performance of southern rural schools, factors affecting rural students' college attendance, and the influence of changing labor markets. (SV)
1999-12-01
Influence of current needs on the advancement of aluminum electrolytic capacitors
The need for cost effective, high performance, long life capacitors with improved reliability is discussed. It is shown that a low cost, miniature aluminum capacitor, with improved reliability and proven life, can be produced with existing technology. It is further shown that the capacitor can be specified for 125 C life and shelf test requirements, and meet established standards for their parametric performance.
1981-06-01
Conversion of biomass, prediction and solution methods for ash agglomeration and related problems
Energy Technology Data Exchange (ETDEWEB)
When biomass is used as fuel for thermal conversion plants, minerals from the fuel can be responsible for major problems. Generally, these problems are associated with the existence and development of low melting compounds or eutectics, which form sticky layers. In a fluidised bed, this can result in bed-agglomeration and defluidisation. This causes local high temperature, which often accelerates the process. It ultimately can lead to a completely sintered bed content with a glassy phase gluing the bed particles together and shut-down of the plant. The main objective of the title project is to develop a methodology to predict ash/bed agglomeration and sintering problems, to indicate related problems and, furthermore, to identify solution methods to make different types of biomass streams more viable for energy production. Within the present study, selected fuels are subjected to different existing methods together with some new ones, in order to determine the agglomeration temperature. ...
1999-11-01
Performance-Aware Power Management in Embedded Controllers with Multiple-Voltage Processors
The goal of this work is to minimize the energy dissipation of embedded controllers without jeopardizing the quality of control (QoC). Taking advantage of the dynamic voltage scaling (DVS) technology, this paper develops a performance-aware power management scheme for embedded controllers with processors that allow multiple voltage levels. The periods of control tasks are adapted online with respect to the current QoC, thus facilitating additional energy reduction over standard DVS. To avoid the waste of CPU resources as a result of the discrete voltage levels, a resource reclaiming mechanism is employed to maximize the CPU utilization and also to improve the QoC. Simulations are conducted to evaluate the performance of the proposed scheme. Compared with the optimal standard DVS scheme, the proposed scheme is shown to be able to save remarkably more energy while maintaining comparable QoC.
2008-01-01
Incorporation of organizational failures in PSA
International Nuclear Information System (INIS)
A large portion of the work performed at nuclear power plants follows standardized flow paths. For example, although components on which the maintenance crew works differ from one assignment to the next, all assignments basically follow the same process: requesting, reviewing, planning, scheduling, executing, testing, and documenting the work. In general, the term open-quotes work processclose quotes is used to refer to a standardized sequence of tasks designed within the operational environment of an organization to achieve a specific goal. The predictable nature of work processes suggests that a systematic analysis can be conducted to identify the desirable design of the process and to develop performance measures with respect to the strengths and weaknesses in the process. Furthermore, because of the close relationship of the work process to plant performance and plant safety, it ...
1993-06-20
New comparative tests on two different types of solar collectors are presented in this paper. A standard glazed flat plate collector and an evacuated tube collector are installed in parallel and tested at the same working conditions; the evacuated collector is a direct flow through type with external compound parabolic concentrator (CPC) reflectors. Efficiency in steady-state and quasi-dynamic conditions is measured following the standard and it is compared with the input/output curves measured for the whole day. The first purpose of the present work is the comparison of results in steady-state and quasi-dynamic test methods both for flat plate and evacuated tube collectors. Besides this, the objective is to characterize and to compare the daily energy performance of these two types of collectors. An effective mean for describing and analyzing the daily performance is the so called input/output diagram, ...
2010-08-15
Energy Technology Data Exchange (ETDEWEB)
A couple of domestic institutions have been investigating the application of vitrification technology to treat low- and intermediate-level radioactive wastes in Korea. In the case that such investigations prove to be successful, it is expected that commercial vitrification plants will be constructed. The safety insuring on vitrification plants could not be compatible with criterion on radioactive waste management because the facilities are at high temperature and contain a variety of accommodations for the exhaust gases and residual products. Therefore, it is necessary to suggest a new strategy or modifications of criterion of radioactive waste management on considerations related with the vitrification technology. In order to ensure the safety of vitrification plants, a technical guideline or standard for design and operation of vitrification plants must be established too. A study on the safety assessment of vitrification plants in ...
2003-02-25
Mixed Waste Management Facility (MWMF) groundwater monitoring report, second quarter 1992
Energy Technology Data Exchange (ETDEWEB)
During second quarter 1992, tritium, trichloroethylene, tetrachloroethylene, chloroethene, antimony, 1,1-dichloroethylene, lead, nonvolatile beta, radium-228, thorium-228, or total alpha-emitting radium (radium-226 and radium-228) exceeded the US Environmental Protection Agency Primary Drinking Water Standards (PDWS) in groundwater samples from monitoring wells at the Mixed Waste Management Facility (MWMF) and adjacent facilities. Tritium and trichloroethylene were the most widespread constituents; 55 (48%) of the 115 monitored wells contained elevated tritium activities, and 23 (20%) wells exhibited elevated trichloroethylene concentrations. Sixty-three downgradient wells screened in Aquifer Zone IIB2 (Water Table), Aquifer Zone IIB[sub 2] (Barnwell/McBean), and Aquifer Unit IIA (Congaree) contained concentrations of tritium, trichloroethylene, tetrachloroethylene, chloroethene, antimony, 1,1-dichloroethylene, lead, ...
1992-09-01
Energy Technology Data Exchange (ETDEWEB)
Urban type R D (research and development) facilities have research institute functions which are not desirable to coexist in a city as compared with suburban R D facilities. Therefore careful consideration must be given to environmental protection. KSP is the first large scale urban type R D facility in Japan. The planning and construction have been made with the theme of realization of flexibility in architecture and mechanical planning as well as realization of environmental integrity. To achieve the target so-called technical slit is built at the center of the building to provide a void space for securing natural ventilation. It is effective for provision of internal mechanical spaces without spoiling urban View air exhaust from laboratories natural ventilation for underground parking lots and decrease of damage by strong wind on the ground level. Standards are established and organization is formed ...
1991-12-05
Psychological test performance in foundry workers exposed to low levels of manganese
Energy Technology Data Exchange (ETDEWEB)
A sample of 30 manganese-exposed foundry workers from two Swedish plants were examined with a partly computerized psychological test battery, comprised of 10 performance tests. Performance of the manganese-exposed workers was compared to that of a matched control group of 60 workers. Matching criteria were age, geographical area, type of work, and the results on a test of verbal comprehension. Performance of the exposed workers was inferior to that of the control group on tests of simple reaction time, digit span, and finger tapping. No correlations were found between performance and the present manganese exposure levels or the number of years employed in manganese work. The results seem to indicate that the present exposure standards for manganese, in Sweden 2.5 mg/m3 and in most other countries 5 mg/m3, are not sufficient to protect workers from negative effects on ...
1990-11-01
ETE-EVAL: a methodology for D and D cost estimation
International Nuclear Information System (INIS)
In compliance with Article 20 of the sustainable radioactive materials and waste management act dated 28 June 2006, the CEA and AREVA are required every three years to revise the cost of decommissioning their facilities and to provide the necessary assets by constituting a dedicated fund. For the 2007 revision the CEA used ETE-EVAL V5. Similarly, AREVA reevaluated the cost of decontaminating and dismantling its facilities at La Hague, as the previous estimate in 2004 did not take into account the complete cleanup of all the structural work. ETE-EVAL V5 is a computer application designed to estimate the cost of decontamination and dismantling of basic nuclear installations (INB). It has been qualified by Bureau Veritas and audited. ETE-EVAL V5 has become the official software for cost assessment of CEA civilian and AREVA decommissioning projects. It has been used by the DPAD (Decontamination and Dismantling Projects Department) cost assessment ...
Implementation plan: Quality assurance requirements: Hazardous Waste Remedial Actions Program
International Nuclear Information System (INIS)
This document establishes the Quality Assurance (QA) Program requirements for the Hazards Waste remedial Actions Program (HASWRAP) for ensuring, with a high degree of confidence, that program objectives will be achieved as planned. The QA Program is introduced in Sect. 1. The HAZWRAP Support Contractor Office (SCO) functional organization and QA responsibilities are shown in Sect. 2. QA program requirements are contained in Sect. 3. These requiremens are pased on the American national Standard, American National Standards Institute/American Society of Mechanical Engineers NQA-1 Quality Assurance Program Requirements for Nuclear Facilities. The 18 elements defined in the standard are tailored to HAZWRAP's needs. The QA program requirements are delineated under the major headings: Quality Assurance Program, Organization, and Control of Quality;two additional program requirements, Software Quality ...
Air conditioner for radioactive material handling facility
Energy Technology Data Exchange (ETDEWEB)
An air conditioner intakes open-air from an open-air intake port to remove sands and sea salt particles by air filters. Then, natural and artificial radioactive particles of less than 1 {mu}m are removed by high performance particulate filters. After controlling the temperature by an air heater or an air cooler, air is sent to each of chambers in a facility under pressure elevation by a blower. In this case, glass fibers are used as the filter material for the high performance particulate filter, which has a performance of more than 99.97% for the particles of 0.3 {mu}m grain size. Since this can sufficiently remove the natural radioactive materials intruded from the outside, a detection limit value in each of the chambers of the facility can be set 10{sup -13} to 10{sup -14} {mu}ci/cm{sup 3} in respect of radiation control. Accordingly, radiation control can be conducted smoothly ...
1991-04-26
On the application of Allan variance method for Ring Laser Gyro performance characterization
Energy Technology Data Exchange (ETDEWEB)
This report describes the method of Allan variance and its application to the characterization of a Ring Laser Gyro`s (RLG) performance. Allan variance, a time domain analysis technique, is an accepted IEEE standard for gyro specifications. The method was initially developed by David Allan of the National Bureau of Standards to quantify the error statistics of a Cesium beam frequency standard employed as the US Frequency Standards in 1960`s. The method can, in general, be applied to analyze the error characteristics of any precision measurement instrument. The key attribute of the method is that it allows for a finer, easier characterization and identification of error sources and their contribution to the overall noise statistics. This report presents an overview of the method, explains the relationship between Allan variance and power spectral density distribution of underlying ...
1993-10-15
Probing anomalous top-quark couplings induced by dim.6 operators at photon colliders
International Nuclear Information System (INIS)
Possible anomalous top-quark couplings induced by SU(2)xU(1) gauge-invariant dimension-6 effective operators were studied in the process of ttbar productions and decays at polarized #gamma##gamma# colliders. Two CP-violating asymmetries, a linear-polarization asymmetry and a circular-polarization asymmetry, were computed including both non-standard ttbar#gamma# and #gamma##gamma#H couplings. An optimal-observable analysis for the process #gamma##gamma##->#ttbar#->#l"#+-# was performed in order to estimate the precision for determination of all relevant non-standard couplings, including the anomalous tbW coupling.
2004-06-21
Evaluation of an ELISA for the diagnosis of brucellosis.
Brucela serology using ELISA and standard agglutination test was performed on 23 patients with prolonged fever where the test was requested, on 26 randomly chosen patients with prolonged fever where it was not requested and on 17 controls. ELISA was positive in 39.1, 26.9 and 0 per cent respectively in these groups. Brucellosis may often be unsuspected because of its varied clinical manifestations and may be a more important cause of fever than previously considered. Our data reaffirm that ELISA is superior to the standard agglutination test for the diagnosis of brucellosis. PMID:8707374
1996-06-01
Development of regulatory techniques for operational performance evaluation of nuclear power plants
Energy Technology Data Exchange (ETDEWEB)
In this study, the state-of-the art for estimating LERF is considered for the regulatory risk-informed decisions. The consideration is mainly focused on (1) the relationship between Level 2 PSA and LERF evaluation methodology, (2) the standard requirements in terms of modeling preparation and the acceptance criteria based on the application capability II of ASME PRA standard, and (3) some pending issues for developing and proposing a simplified LERF model. This study is preliminarily presented and will be updated for establishing detailed evaluation scheme of extended MPAS (multi-purpose probabilistic analysis of safety) model and preparing the technical basis.
2006-01-15
The Path to Metallicity: Synthesis of CNO Elements inStandard BBN
Energy Technology Data Exchange (ETDEWEB)
We perform an analysis of the production of elements with mass number A {ge} 12 in a standard Big Bang Nucleosynthesis scenario. The goal is to provide a more accurate estimate of the very low and yet poorly explored abundance of such elements, relevant for the pristine Population III stars. We examine the synthesis channels for these elements in a critically revised and updated version of the Wagoner-Kawano code, as well as in a further enlarged version including four additional nuclides and a significantly extended nuclear network. Our results show no major discrepancies with the ones obtained using a smaller nuclear network. The robustness of the standard predictions--the early generation of star developed in a metal-free environment--is confirmed.
2007-02-12
Technical Standards for Wolsong Unit 1 Nuclear Power Plant
International Nuclear Information System (INIS)
More than twenty years after commencing commercial operation in 1983, Wolsong Unit 1(W1- NPP), the first CANDU Pressurized Heavy Water Reactor (PHWR) in Korea, has been undergoing refurbishment. Safety analyses were required to evaluate the safety of W1-NPP because significant amount of equipment has been refurbished. To evaluate the effectiveness of W1-NPP after these upgrades, new safety analyses were performed using the same technical standards of Wolsong Units 2, 3, 4 (W234-NPP) for Design Basis Accidents (DBA). The refurbished W1- NPP is expected to be licensed for full power operation based on the verified safety analysis results that are obtained by using the upgraded computer codes and newly adopted technical standards of W234-NPP
2010-10-01
Performance Testing Methodology for Safety-Critical Programmable Logic Controller
International Nuclear Information System (INIS)
The Programmable Logic Controller (PLC) for use in Nuclear Power Plant safety-related applications is being developed and tested first time in Korea. This safety-related PLC is being developed with requirements of regulatory guideline and industry standards for safety system. To test that the quality of the developed PLC is sufficient to be used in safety critical system, document review and various product testings were performed over the development documents for S/W, H/W, and V/V. This paper provides the performance testing methodology and its effectiveness for PLC platform conducted by KOPEC
2009-05-01
Energy Technology Data Exchange (ETDEWEB)
This work demonstrate the gasoline volatility influence, at T 10%, T 50% and T 90% distillation points, on the dynamic performance of Otto cycle engines equipped with fuel sequential electronic injection system, by using test standard procedures in dynamometer. For each distillation points three value ranges were established, giving the rise of 27 different gasoline mixtures. The effects of variation in each point on consumption, power and acceleration were verified.
1998-07-01
Operational procedures - industry observations and opportunities for improvement
Energy Technology Data Exchange (ETDEWEB)
The purpose of this paper is to relate some of the commonly encountered problems with operational procedures in the nuclear industry and offer practical suggestions for their elimination. The paper is based on recent consultant experience in assisting industry clients with human performance related design and assessment initiatives. Operational procedures are a key part of an integrated system design. Procedures provide the specified instructions for actions people are to undertake in operating a facility to achieve production and safety goals. While organizations continue to make substantial investments in procedure development and maintenance, problems with procedures continue to occur, as evidenced through operating inefficiencies, errors, and events. The paper reviews the role procedures play in facility operations, comments on current development and maintenance practices, discusses the extent of human ...
2003-07-01
Fabrication of core demonstration experiments for irradiation in the FFTF [Fast Flux Test Facility
International Nuclear Information System (INIS)
A major new initiative to develop and irradiate a long-lived, mixed-oxide (MOX) fuel system in the Fast Flux Test Facility (FFTF) has been implemented by Westinghouse Hanford Company for the U.S. Department of Energy. The purpose of this new fuel system, called the core demonstration experiment (CDE), is to demonstrate the capability of achieving a 3-yr life in a prototypical, heterogeneous reactor environment under prototypical power and temperature conditions. Ten fuel and six blanket CDEs are establishing the performance characteristics of entire fuel assemblies of wire-wrapped, large-diameter, annular-pellet, advanced MOX fuel pins with the tempered martensitic HT-9 alloy cladding and end caps, HT-9 wire wrap, and an HT-9 duct in a heterogeneous array with the blanket assemblies. The CDE performance characteristics are confirming the basis for design, fabrication, and irradiation of the CDE.
1990-06-10
FFTF [Fast Flux Test Facility] reactor shutdown system reliability reevaluation
International Nuclear Information System (INIS)
The reliability analysis of the Fast Flux Test Facility reactor shutdown system was reevaluated. Failure information based on five years of plant operating experience was used to verify original reliability numbers or to establish new ones. Also, system modifications made subsequent to performance of the original analysis were incorporated into the reevaluation. Reliability calculations and sensitivity analyses were performed using a commercially available spreadsheet on a personal computer. The spreadsheet was configured so that future failures could be tracked and compared with expected failures. A number of recommendations resulted from the reevaluation including both increased and decreased surveillance intervals. All recommendations were based on meeting or exceeding existing reliability goals. Considerable cost savings will be incurred upon implementation of the recommendations.
FFTF (Fast Flux Test Facility) reactor shutdown system reliability reevaluation
Energy Technology Data Exchange (ETDEWEB)
The reliability analysis of the Fast Flux Test Facility reactor shutdown system was reevaluated. Failure information based on five years of plant operating experience was used to verify original reliability numbers or to establish new ones. Also, system modifications made subsequent to performance of the original analysis were incorporated into the reevaluation. Reliability calculations and sensitivity analyses were performed using a commercially available spreadsheet on a personal computer. The spreadsheet was configured so that future failures could be tracked and compared with expected failures. A number of recommendations resulted from the reevaluation including both increased and decreased surveillance intervals. All recommendations were based on meeting or exceeding existing reliability goals. Considerable cost savings will be incurred upon implementation of the recommendations.
1986-07-01
CANDU 6 fuel behaviour in power ramp conditions
International Nuclear Information System (INIS)
The facilities in the Institute for Nuclear Research at Pitesti allow the testing, handling and examination of nuclear fuel and irradiated materials. The most important facilities are the TRIGA Steady State Research and Material Test Reactor and the Post-Irradiation Examination Laboratory (PIEL). The purpose of this work is to determine by post-irradiation examination, the behavior of CANDU fuel, irradiated in 14 MW TRIGA reactor. The fuel was irradiated in power ramp conditions. The results of post-irradiation examination are: - Visual inspection and photography of the outer appearance of sheath; - Profilometry (diameter, bending, ovality) and length measuring; - Determination of axial and radial distribution of the fusion products activity by gamma scanning and tomography; - Microstructural characterization by metallographic and ceramographic analyzes; - Mechanical properties determination. The data obtained from the post-irradiation ...
2009-10-12
International Nuclear Information System (INIS)
Many types of maintenance activities are performed on contaminated (radioactive) machines and components at the Fast Flux Test Facility (FFTF). When personnel dose levels are within permissible limits, maintenance is performed in contaminated work areas or in gloveboxes. Otherwise, maintenance is performed in the Interim Examination and Maintenance (IEM) Cell, a hot cell that is used to perform tasks that require remote operation. Maintenance is often a combination of manual and remote operation. One such operation was the cleaning of the closed loop ex-vessel machine (CLEM) core component grapple (CCG). The CLEM is used to transfer core components in and out of the reactor vessel. The CCG had not been operating properly due to buildups of metallic sodium and sodium compounds on the outside surface and internal moving parts. This paper tells how the CCG was disassembled and cleaned. ...
1990-11-11
Energy Technology Data Exchange (ETDEWEB)
The theoretical performance of ideal single- and multijunction cells are compared at 100xconcentration under a range of cloudless-sky conditions. The sensitivities of device performance to cell temperature and spectral variations are shown to depend on the number of junctions (one, two or three), the way in which the junctions are connected (series, parallel or independent), and the band gaps of the devices. The average performances of all of the multijunction devices surpass that of a single-junction GaAs device, but the inconsistency in performance of some of the multijunction devices is significant for large variations in cell temperature and incident spectrum. The choice of band gap and connection scheme is more important than the number of junctions in determining the consistency of device performance. (orig.).
1991-05-01
Waste Handeling Building Conceptual Study
Energy Technology Data Exchange (ETDEWEB)
The objective of the ''Waste Handling Building Conceptual Study'' is to develop proposed design requirements for the repository Waste Handling System in sufficient detail to allow the surface facility design to proceed to the License Application effort if the proposed requirements are approved by DOE. Proposed requirements were developed to further refine waste handling facility performance characteristics and design constraints with an emphasis on supporting modular construction, minimizing fuel inventory, and optimizing facility maintainability and dry handling operations. To meet this objective, this study attempts to provide an alternative design to the Site Recommendation design that is flexible, simple, reliable, and can be constructed in phases. The design concept will be input to the ''Modular Design/Construction and Operation Options ...
2000-11-06
Examination of scaling criteria for nuclear reactor thermal-hydraulic test facilities
International Nuclear Information System (INIS)
Scaling criteria for a natural-circulation loop are examined. The present state of knowledge of scaling to obtain similarity during single- and two-phase flow conditions in a closed loop are reviewed, and an alternative development of two-phase similarity parameters is presented. The loop scaling criteria are the results of analyses in which flow from one component to another is considered. In this work, boundary conditions for the closed loop are developed to obtain scaling criteria for leak flow, injection flow, and heat loss to ambient. The leak scaling criteria are specialized for modeling approaches using prototypic fluid at prototypic or reduced pressures. The derived scaling parameters are examined for their application to two existing scaled test facilities: the Multi-Loop Integral System Test (MIST) facility at Babcock and Wilcox, and the UMCP 2 x 4 facility at the University of Maryland College Park. The heat loss ...
1987-01-01
Entombment Using Cementitious Materials: Design Considerations and International Experience
Energy Technology Data Exchange (ETDEWEB)
Cementitious materials have physical and chemical properties that are well suited for the requirements of radioactive waste management. Namely, the materials have low permeability and durability that is consistent with the time frame required for short-lived radionuclides to decay. Furthermore, cementitious materials can provide a long-term chemical environment that substantially reduces the mobility of some long-lived radionuclides of concern for decommissioning (e.g., C-14, Ni-63, Ni-59). Because of these properties, cementitious materials are common in low-level radioactive waste disposal facilities throughout the world and are an attractive option for entombment of nuclear facilities. This paper describes design considerations for cementitious barriers in the context of performance over time frames of a few hundreds of years (directed toward short-lived radionuclides) and time frames of thousands of years (directed ...
2002-08-01
Entombment Using Cementitious Materials: Design Considerations and International Experience
Energy Technology Data Exchange (ETDEWEB)
Cementitious materials have physical and chemical properties that are well suited for the requirements of radioactive waste management. Namely, the materials have low permeability and durability that is consistent with the time frame required for short-lived radionuclides to decay. Furthermore, cementitious materials can provide a long-term chemical environment that substantially reduces the mobility of some long-lived radionuclides of concern for decommissioning (e.g., C-14, Ni-63, Ni-59). Because of these properties, cementitious materials are common in low-level radioactive waste disposal facilities throughout the world and are an attractive option for entombment of nuclear facilities. This paper describes design considerations for cementitious barriers in the context of performance over time frames of a few hundreds of years (directed toward short-lived radionuclides) and time frames of thousands of years (directed ...
2002-05-15
Conversion of the Midland nuclear station
Energy Technology Data Exchange (ETDEWEB)
The authors report how the Midland cogeneration venture (MCV) is repowering the incomplete Midland nuclear plant to operate as a gas-fired combined cycle cogeneration facility. They discuss how their company is responsible for performing engineering, procurement, licensing, construction, start-up, training, and operational assistance for this facility. As shown, twelve gas turbine generator sets supply heat to twelve heat recovery steam generators (HRSGs), which are headered together on the steam side to provide energy to either of two existing steam turbine generators. This combination of equipment enables approximately 1,380 MWe of electrical generation capability, while supplying an average steam flow of 629,000 lbs/hr to an adjacent Dow Chemical Company pant. The MCV facility will also provide 60 MW of electric power to Dow. The authors report how the Midland ccogeneration venture (MCV) is ...
1988-01-01
Energy Technology Data Exchange (ETDEWEB)
A Lawrence Livermore National Laboratory (LLNL) Management Pre-Start Review (MPR) Team was formed to independently verify the operational readiness of Building 368 (B368) Biosafety Level III (BSL-3) Facility to conduct research with biological pathogens and toxins including those considered Select Agents. Review objectives and criteria were developed from the DOE/NNSA and LLNL requirements. These were provided in the Implementation Plan for the Biosafety Level III (BSL-3) Facility Management Pre-Start Review (BSL-3 MPR) at Lawrence Livermore National Laboratory that was reviewed and approved by DOE/NNSA-LSO. The formal part of the LLNL MPR for the BSL-3 Facility was begun in August of 2005 but work on the MPR was stopped in October of 2005 due to the need for LLNL to reassess organizational and operational controls and respond to Centers for Disease Control and Prevention inquiries related to a shipping incident involving ...
2006-07-25
British Library Electronic Table of Contents (United Kingdom)
The objective of this study is to analyze the effects of heat loss characterized by a percentage of the fuel's energy, friction and variable specific heats of working fluid on the performance of an air standard Otto cycle with a restriction of maximum cycle temperature. A more realistic and precise relationship between the fuel's chemical energy and the heat leakage that is based on a pair of inequalities is derived through the resulting temperature. The variations in power output and thermal efficiency with compression ratio, and the relations between the power output and the thermal efficiency of the cycle are presented. The results show that the power output as well as the efficiency where maximum power output occurs will increase with increase of the maximum cycle temperature. The temp...
2008-01-01
The Vortec Cyclone Melting System (CMS) facility; to be located at the U.S. Department of Energy (DOE) Paducah Gaseous Diffusion Plant, is designed to treat soil contaminated with low levels of heavy metals and radioactive elements, as well as organic waste. The primary components of Vortec`s CMS are a counter rotating vortex (CRV) reactor and cyclone melter. In the CMS process, granular glass forming ingredients and other feedstocks are introduced into the CRV reactor where the intense CRV mixing allows the mixture to achieve a stable reaction and rapid heating of the feedstock materials. Organic contaminants in the feedstock are effectively oxidized, and the inert inorganic solids are melted. The University of North Dakota Energy {ampersand} Environmental Research Center (EERC) has been contacted to help in the development of sampling plans and to conduct the sampling at the facility. This document is written in a format that assumes that the ...
1997-12-31
This report presents the results of Run 261 performed at the Advanced Coal Liquefaction R & D Facility in Wilsonville, Alabama. The run started on January 12, 1991 and continued until May 31, 1991, operating in the Close-Coupled Integrated Two-Stage Liquefaction mode processing Illinois No. 6 seam bituminous coal (from Burning star No. 2 mine). In the first part of Run 261, a new bimodal catalyst, EXP-AO-60, was tested for its performance and attrition characteristics in the catalytic/catalytic mode of the CC-ITSL process. The main objective of this part of the run was to obtain good process performance in the low/high temperature mode of operation along with well-defined distillation product end boiling points. In the second part of Run 261, Criterion (Shell) 324 catalyst was tested. The objective of this test was to evaluate the operational stability and catalyst and process ...
1992-09-01
Topical Report ''Corrosion Evaluation of LLW2 Skid-B Weld Failure Mechanisms (44139-92)
Energy Technology Data Exchange (ETDEWEB)
An independent investigation of pipe welding leaks from the Low-Level Waste 2 (LLW2) Skid-B System for the possibilities of improper welding (IW), microbiologically influenced corrosion (MIC), sensitization, chloride pitting corrosion (CPC), and intergranular stress corrosion cracking (IGSCC) was conducted. The results show the prevailing mechanisms that caused the leaks are identified as IW, CPC, and the improper selection of weld filler material for the base metals in an environment of the North Plateau underground water. These is no evidence of MIC, sensitization, or IGSCC. The chloride pitting corrosion mechanism that took place at all the welds are also described. All the pipelines were replaced with polyvinyl chloride (PVC) for cost saving and the LLW2 Skid B System has been successfully operating since 1999. This report summarizes the findings and recommendations associated with preventive measures for future operations. The LLW2 Facility is a replacement ...
2001-05-31
Performance of hydrous titanium oxide-supported catalysts in coal-liquids upgrading
Experimental tests were performed in a continuous-flow hydrotreating unit at Pittsburgh Energy Technology Center to evaluate the performance of hydrous titanium-oxide supported (HTO) catalysts as hydrotreating catalysts for use in two-stage coal liquiefaction. Catalysts containing either a combination of CO, Ni, and Mo as the active metal components or Pd as the active metal componet were tested with representative hydrotreater feed stocks from the Wilsonville Advanced Coal Liquefaction Research and Development Facility. Catalyst performance evaluation was based on desulfurization and denitrogenation activity, the conversion of cyclohexane-insolbule material, and hydrogenation activity during 100-hour reactor runs. Results indicated that the HTO catalysts were comparable to a commercial Ni/Mo-alumina supported catalyst in the areas evaluated. 11 refs., 1 fig., 6 tabs.
1988-01-01
Progress at LAMPF. Progress report, January-December 1985
Energy Technology Data Exchange (ETDEWEB)
Research performed at LAMPF during 1985 is reported in the areas of: nuclear and particle physics; atomic and molecular physics; materials science; radiation-effects studies; biomedical research and instrumentation; nuclear chemistry; radioisotope production; and physics theory. Also reported are the status of LAMPF-II, facility development work, and accelerator operations. (LEW)
1986-05-01
Pollution control instrumentation for oil and effluents
Energy Technology Data Exchange (ETDEWEB)
This book provides discusses recent developments in oil pollution control instrumentation. Some of the topics covered are as follows: 1. Technical requirements of the IMCO International Performance and Test Specification A393x concerning oil content meters; and 2. Oil in water detection; and 3. Methods for the disposal of recovered oil and oily sludge; and 4. Oil content monitoring at ballast water treatment facilities and offshore production platforms.
1986-01-01
Leveraging limited research and development (R&D) resources in the public sector
Energy Technology Data Exchange (ETDEWEB)
Mission-directed public-sector research facilities are experiencing increasingly severe budget environments while seeing expanding missions and responsibilities. In an effort to identify research leveraging methodologies an information search was conducted in conjunction with some efforts to find the proper links to systems engineering fundamentals. The result is an initial model for use in a pre-concept/phase-1 engineering design organization, with a goal of improving the organizations performance.
1996-12-01
KEROGEN OIL VALUE ENHANCEMENT RESEARCH
Energy Technology Data Exchange (ETDEWEB)
Task 13 (a) was approved on December 21, 2001. Minimal work was performed for the quarter during the approval process. Laboratory and equipment facilities have been maintained in anticipation of the work to be done. The PI communicated with DOE and Estonia researchers during this period, providing advice and direction for the startup of the Estonia research, and preparing a Draft Teaming Agreement. The PI participated in an industrial liaison meeting with DOE personnel. This meeting is expected to lead to formal cooperation between industry and government.
2002-01-11
Irradiation data for the MFA-1 and MFA-2 tests in the FFTF
Energy Technology Data Exchange (ETDEWEB)
This report provides key information on the irradiation environment of the MONJU fuel tests MFA-1 and MFA-2 in the Fast Flux Test Facility (FFTF). This information includes the fission powers, neutron fluxes, sodium temperatures and sodium flow rates in MFA-I, MFA-2 and adjacent assemblies. It also includes MFA-1 and MFA-2 compositions as a function of exposure. The work was performed at the request of Power Reactor and Nuclear Fuels Corporation (PNC) of Japan.
1997-04-24
Hot Particles Research for Nuclear Power Plant in Wolsung
Energy Technology Data Exchange (ETDEWEB)
The evaluation of the hazard posed to the skin by very small radioactive sources (diameter < 1mm) has become popularly known as the 'hot particle' problem in European and American nuclear reactor facilities. In this study, research to detect hot particle was performed in Wolsung Nuclear power plant (NPP) in Korea.
2007-10-15
Hot Particles Research for Nuclear Power Plant in Wolsung
International Nuclear Information System (INIS)
The evaluation of the hazard posed to the skin by very small radioactive sources (diameter < 1mm) has become popularly known as the 'hot particle' problem in European and American nuclear reactor facilities. In this study, research to detect hot particle was performed in Wolsung Nuclear power plant (NPP) in Korea.
2007-10-01
Energy analysis for Fort McNair, Marshall Hall
Marshall Hall was selected by the US Army Corps of Engineers to participate in the Energy Efficiency Analysis Program. The objective of this program is to assist military installations in identifying energy usage and cost saving projects at their facilities and possibly provide funding for projects. Entech Engineering, Inc. was selected to perform this study.
1995-08-01
Assessing predictive skill of models to optimise crop management and design
Environmental Research Database
DescriptionAn ability to foresee impacts on output is invaluable to any industry; good prediction is the basis of good management. Many research models can predict crop performance, but the skill (used here to include accuracy, precision, facility and credibility) of these predictions is rarely assessed, so is not well known. The only research model successfully adopted for practical purposes in the UK is the Broom's Barn Beet Model. Thus we propose here, research to assess and publish the skill of the [continued...
2004-01-30
Thermal performance and design of a solid particle cavity receiver
Energy Technology Data Exchange (ETDEWEB)
A model for energy transport in a solid particle cavity receiver is developed and applied to the design and analysis of a receiver for the Central Receiver Test Facility (CRTF), Albuquerque, New Mexico. The model gives thermal performance results - including particle temperatures, cavity efficiencies, and wall temperatures - which directly affect the economic and technical feasibility of a solid particle receiver. In addition, design criteria relevant to the configuration of a solid particle cavity receiver are developed. Results for CRTF indicate that at design conditions particle temperatures will exceed 1200/sup 0/K with cavity efficiencies on the order of 75%.
1985-04-01
High power evaluation of X-band high power loads
Several types of X-band high power loads developed for several tens of MW range were designed, fabricated and used for high power tests at X-band facility of KEK. Some of them have been used for many years and few units showed possible deterioration of RF performance. Recently revised-design loads were made by CERN and the high power evaluation was performed at KEK. In this paper, the main requirements are recalled, together with the design features. The high power test results are analysed and presented
2010-01-01
Development of the SRS environmental counting laboratory gamma spectroscopy system
International Nuclear Information System (INIS)
The Savannah River Site (SRS), one of several U.S. Department of Energy (DOE) facilities, produces nuclear materials for national defense and for other government and civilian uses. SRS ceased production of defense materials in 1988, and the site's main activities now involve waste management and environmental restoration. These programs have generated extensive effluent monitoring and environmental surveillance programs for the Environmental Monitoring Section (EMS), which performs #approx#105,000 radiological analyses on 30,000 samples a year. Gamma spectroscopy is performed on an estimated 10,000 samples annually. This report describes a program to develop and improve the EMS system.
1996-06-16
Combustion performance of Coal Valley coal in a pilot-scale utility boiler. Report No. ERL 87-18(CF)
Energy Technology Data Exchange (ETDEWEB)
Combustion performance trials were conducted on a commercial sample of Coal Valley coal from the Coalspur coalfield in the foothills region of Alberta. The project included an analytical investigation of the coal and coal ash properties as well as combustion studies in the CCRL pilot-scale, pulverized coal-fired boiler, under conditions representative of those in large steam boilers. This report gives the objectives of the project, the analyses of the coals, and describes the facilities and operational procedures. An evaluation of the experimental results and the conclusions are presented.
1987-01-01
CLEO: a knowledge-based refueling assistant at FFTF
International Nuclear Information System (INIS)
A computer software system, CLEO, is used to assist in the planning and performance of the reactor refueling operations at the Fast Flux Test Facility (FFTF). It is a recently developed application of artificial intelligence software with both expert systems and automated reasoning aspects. CLEO, an acronym for Cloned LEO, is a logic-based computer program written in Pascal. It imitates the processes that the refueling expert for FFTF performs in organizing the refueling of FFTF. The computer assistant seeks to organize the sequence of core component movements according to the rules and logic used by the expert. In this form, CLEO has aspects that tie it to both the expert systems and automated reasoning areas within the artificial intelligence field.
1985-11-10
University of Central Lancashire - Facilities
...specialised laboratories for pharmaceutics, tissue culture and molecular biology Excellent Laboratory Facilities Tissue Culture Facilities Molecular Biology Laboratory ...
International Nuclear Information System (INIS)
On March 31, 1995, the US Department of Energy filed a draft application for certification of compliance with the US Environmental Protection Agency (USEPA) to show the Waste Isolation Pilot Plant's compliance with the USEPA's environmental standards, making the application the first of its kind. Demonstration of compliance is by performance assessment. This paper is an early review of the performance assessment in the draft application, by the Environmental Evaluation Group, an oversight group. The performance assessment in the draft application is incomplete. Not all relevant scenarios have been analyzed. The calculation of potential consequences often does not use experimental data but rather estimates by workers developing additional data. The final compliance application, scheduled for October 1996 needs to consider additional scenarios, and be fully based on experimental data.
Spent Fuel Background Report Volume I
Energy Technology Data Exchange (ETDEWEB)
This report is an overview of current spent nuclear fuel management in the DOE complex. Sources of information include published literature, internal DOE documents, interviews with site personnel, and information provided by individual sites. Much of the specific information on facilities and fuels was provided by the DOE sites in response to the questionnaire for data for spent fuels and facilities data bases. This information is as accurate as is currently available, but is subject to revision pending results of further data calls. Spent fuel is broadly classified into three categories: (a) production fuels, (b) special fuels, and (c) naval fuels. Production fuels, comprising about 80% of the total inventory, are those used at Hanford and Savannah River to produce nuclear materials for defense. Special fuels are those used in a wide variety of research, development, and testing activities. Special fuels include fuel from DOE and commercial ...
1994-03-01
Large sample NAA facility at GRR-1 research reactor: Design and applications
International Nuclear Information System (INIS)
Full text: A Large Sample Neutron Activation Analysis (LSNAA) facility is under development at GRR-1 research reactor, NCSR 'Demokritos'. The LSNAA facility design incorporates sample irradiation in the reactor's graphite thermal neutron column and subsequent measurement of the activity induced at a gamma spectroscopy system with gamma ray transmission measurement options included. Monte Carlo neutron and photon transport code MCNP-4C was used to model the facility. Appropriate correction factors accounting for neutron field perturbation during sample irradiation, high purity germanium detector efficiency for the volume source and gamma ray self-absorption within the sample itself were derived. The results of the computations were experimentally verified by activation foil measurements for a set of known materials and a range of sample sizes extending up to 10 litters. Moreover, the special issue of large sample analysis of ...
2003-06-09
Energy Technology Data Exchange (ETDEWEB)
Since enterprises operating offices and facilities at geographically distributed sites have been establishing an intranet for inter-office communication at the management level, the idea of integrating another intranet for multi-site technological facility management comes naturally. The Aachen-based technology enterprise Eurem for this purpose developed a Network and Security concept with solutions that can be customized for linking a variety of computerized control and monitoring systems. The package includes a modular substation named modUS, which is open to the field side as well as to the management side, is capable of efficiently and reliably performing the facility management functions by way of remote controlling via intranets. (orig./CB) [Deutsch] Nachdem in den Unternehmen mit verteilten Liegenschaften die unterschiedlichsten Buerokommunikationssysteme ueber eigene Netzwerke verbunden werden, ...
1999-02-08
Evaluation of performance and characteristics of neutron radiography and standardization
Energy Technology Data Exchange (ETDEWEB)
Neutron radiography has been put to practical use in foreign countries as one of nondestructive inspection technologies, but in Japan, its application to other scientific fields is mainly researched. The reason is, the neutron radiography apparatuses installed in Japan are hard to be industrially utilized for a number of reasons, but also the characteristics of neutron radiography are not clearly established, and it is not standardized. The part from a collimator through an object to a detector is called ``upstream``, the part of an image detector is called ``midstream``, and the part of image processing is called ``downstream``. The nonparallel property of beam, image distortion and the lack of sharpness, beam quality and the interaction of neutron beam with an object are discussed about the upstream. The intensity of neutron beam, the energy spectra, the effective total macroscopic cross section, the effective energy, the evaluation of scattered beam and ...
1995-02-01
Overview of hazardous-waste regulation at federal facilities
Energy Technology Data Exchange (ETDEWEB)
This report is organized in a fashion that is intended to explain the legal duties imposed on officials responsible for hazardous waste at each stage of its existence. Section 2 describes federal hazardous waste laws, explaining the legal meaning of hazardous waste and the protective measures that are required to be taken by its generators, transporters, and storers. In addition, penalties for violation of the standards are summarized, and a special discussion is presented of so-called imminent hazard provisions for handling hazardous waste that immediately threatens public health and safety. Although the focus of Sec. 2 is on RCRA, which is the principal federal law regulating hazardous waste, other federal statutes are discussed as appropriate. Section 3 covers state regulation of hazardous waste. First, Sec. 3 explains the system of state enforcement of the federal RCRA requirements on hazardous waste within their borders. Second, Sec. 3 discusses two peculiar ...
1982-05-01
Nuclear incident monitor criticality alarm instrument for the Savannah River Site: Technical manual
Energy Technology Data Exchange (ETDEWEB)
The Savannah River Site is a Department of Energy facility. The facility stores, processes, and works with fissionable material at a number of locations. Technical standards and US Department of Energy orders, require these locations to be monitored by criticality alarm systems under certain circumstances. The Savannah River Site calls such instruments Nuclear Incident Monitors or NIMs. The Sole purpose of the Nuclear Incident Monitor is to provide an immediate evacuation signal in the case of an accidental criticality in order to minimize personnel exposure to radiation. The new unit is the third generation Nuclear Incident Monitor at the Savannah River Site. The second generation unit was developed in 1979. It was designed to eliminate vacuum-tube circuits, and was the first solid state NIM at SRS. The major design objectives of the second generation NIM were to improve reliability and reduce maintenance costs. Ten ...
1996-05-21
Measurement of gamma-ray detection efficiency in irradiated materials examination facility
Energy Technology Data Exchange (ETDEWEB)
The detection efficiency of gamma scanning system in irradiated materials examination facility has been measured. Gamma-ray sources used in this experiment are Cs-Co standard sources a PWR spent fuel rod in which {sup 134}Cs and {sup 154}Eu peaks are clearly identified in the energy region of 500 to 1,600 keV. The distance between source and detector is about 1.6 m. A slit type collimator with 3 mm-width window and 30 mm-thick lead block are installed between source and detector. The detector is a HPGe detector. This equipment is mainly used in gamma scanning of irradiated nuclear fuel. The measured detection efficiency seems to be 1.89 x 10{sup -6} % for 1 MeV gamma-ray. With these results the activities of unknown sources could be measured. This results are expected to be used in the measurement of the absolute distribution of gamma emitting nuclides in nuclear fuel.
2001-05-01
MTF analysis of the MURR real-time neutron radiography facility
International Nuclear Information System (INIS)
In neutron radiography, as in other forms of NDE, it is sometimes desirable to observe dynamic events. This need has generated increased interest in real-time neutron radiography systems. As in other forms of radiography, a standard method for measuring the image forming capability of real-time systems is necessary in order to compare the various methods and systems used. A technique which has been used extensively in general photography and has been applied in the characterization of several screen-film combinations used in conventional neutron radiography is to determine the imaging system's modulation transfer function (MTF). This gives a graphical representation of the system's spatial resolution capabilities and was therefore chosen as the method for evaluation of the real-time neutron radiography facility at the University of Missouri Research Reactor (MURR). The method used was to image a knife-edge, differentiate the edge gradient to ...
1982-04-01
Groundwater surveillance plan for the Oak Ridge Reservation
Energy Technology Data Exchange (ETDEWEB)
US Department of Energy (DOE) Order 5400.1 requires the preparation of environmental monitoring plans and implementation of environmental monitoring programs for all DOE facilities. The order identifies two distinct components of environmental monitoring, namely effluent monitoring and environmental surveillance. In general, effluent monitoring has the objectives of characterizing contaminants and demonstrating compliance with applicable standards and permit requirements, whereas environmental surveillance has the broader objective of monitoring the effects of DOE activities on on- and off-site environmental and natural resources. The purpose of this document is to support the Environmental Monitoring Plan for the Oak Ridge Reservation (ORR) by describing the groundwater component of the environmental surveillance program for the DOE facilities on the ORR. The distinctions between groundwater effluent monitoring and ...
1994-07-01
International Nuclear Information System (INIS)
One wonders how a facility will cope with the new Clean Air Act Amendments (CAAA). Environmental engineers working in large companies' facilities and in corporate engineering groups already have an idea of how to comply with the regulations for chemical plant equipment leaks. (In fact, the rules will also affect process bins, wastewater, transfer and storage.) But those who work for smaller companies or who have assignments not directly tied to environmental affairs may not have access to the latest thinking on compliance. One of the first challenges in becoming aware of the CAAA regulations is learning the new language, which consists of acronyms, some containing other acronyms. NESHAP, for example, stands for national emissions standards for hazardous air pollutants. Prior to the CAAA, NESHAPs applied to a few specific chemicals, such as benzene. Now the proposed rules establish a HON, a hazardous organic NESHAP. ...
British Library Electronic Table of Contents (United Kingdom)
Objective: The aim of this study was to obtain an overview of the methodological quality of studies on the measurement properties of neck pain and disability questionnaires and to describe how well various aspects of the design and statistical analyses of studies on measurement properties are performed. Methods: A systematic review was performed of published studies on the measurement properties of neck pain and disability questionnaires. Two reviewers independently rated the quality of the studies using the COnsensus-based Standards for the selection of health Measurement INstruments (COSMIN) checklist. This checklist was developed in an international Delphi consensus study. Results: A total of 47 articles were included on the measurement properties of 8 different questionnaires. The meth...
2011-01-01
Factors that influence programming decisions of US symphony orchestras
British Library Electronic Table of Contents (United Kingdom)
Program decisions by symphony orchestra management are influenced by various factors. To examine these factors, we create an objective index of the propensity of a symphony orchestra to perform the standard repertoire. We use regression analysis to examine factors that influence programming decisions of 64 US symphony orchestras in 2006?2007, including public and private sources of funding. We find that increased funding from ticket sales, endowments, and local government increases the likelihood that an orchestra will perform nonstandard repertoire. In addition, the results suggest that a symphony orchestra?s music director does not have a significant impact on the degree of program conventionality.
2011-01-01
International Nuclear Information System (INIS)
Requirements on PSA for risk informed applications are expressed in different international documents. The ASME PRA standard published in spring 2002 is one such document, PSA requirements are also expressed in the European Utility Requirements (EUR) for new reactors. The Swedish PSA requirements are provided in the Swedish regulators (SKI) statutes SKIFS 2004:1. SKI also has a review handbook for PSA activities (SKI report 2003:48). The review handbook is a support during review of the utilities PSA activities and the PSAs themselves. The review handbook expresses SKIs expectations by providing so called important aspects for both the PSA work and the PSAs, A comparison of SKIFS requirements and the important aspects in the Review handbook, on one side, and the requirements on PSA in EUR and ASME on the other side, is presented. The comparison shows a large difference in the level of detail in the different documents, where ASME is most detailed and specific. This ...
1998-11-15
Energy Technology Data Exchange (ETDEWEB)
This book includes the latest developments and covers pump performance, selection and operations, materials, seals and packings, effective fluid characteristics, filtration, piping systems, economics, valves, instrumentation, automatic controls, power transmission equipment, pump and pipeline heating, and more. An extensive data section contains formulas, charts, symbols, nomographs, and standard specification documents.
1984-01-01
Mathematic modeling of the coke gas combustion process
Energy Technology Data Exchange (ETDEWEB)
Analysis of the coke gas combustion porcess is presented. Standard kinetic relationships were utilized. Calculations were performed for coke gas with high and low content of H/sub 2/ and for blasting air 20 and 100/sup 0/C. Temperature relationships, composition of gas combustion products and release of nitrogen oxides were determined. Results are analyzed which will make it possible to control the composition of combustion products.
1983-01-01
Insights from Guideline for Performance of Internal Flooding Probabilistic Risk Assessment (IFPRA)
Energy Technology Data Exchange (ETDEWEB)
An internal flooding (IF) risk assessment refers to the quantitative probabilistic safety assessment (PSA) treatment of flooding as a result of pipe and tank breaks inside the plants, as well as from other recognized flood sources. The industry consensus standard for Internal Events Probabilistic Risk Assessment (ASME-RA-Sb-2005) includes high-level and supporting technical requirements for developing internal flooding probabilistic risk assessment (IFPRA). This industry standard is endorsed in Regulatory Guide 1.200, Revision 1 as an acceptable approach for addressing the risk contribution from IF events for risk informed applications that require U.S. Nuclear Regulatory commission (NRC) approval. In 2006, EPRI published a draft report for IFPRA that addresses the requirements of the ASME PRA consensus standard and have made efforts to refine and update the final EPRI IFPRA guideline. Westinghouse has ...
2009-10-15
Energy Technology Data Exchange (ETDEWEB)
This paper describes the implementations of a fuzzy logic based self-tuned controller to improve the stability of electric power systems. The stabilizing signal is computed using the standard fuzzy membership function depending on the speed/acceleration state of the generator in the phase plane. The performance of the proposed stabilizer is demonstrated by practical implementation using a digital signal processor mounted on a PC-AT. Results of the experimental tests on a physical model of a power system are presented.
1993-06-01
Development of High-Efficiency Low-Lift Vapor Compression System - Final Report
Energy Technology Data Exchange (ETDEWEB)
PNNL, with cofunding from the Bonneville Power Administration (BPA) and Building Technologies Program, conducted a research and development activity targeted at addressing the energy efficiency goals targeted in the BPA roadmap. PNNL investigated an integrated heating, ventilation and air conditioning (HVAC) system option referred to as the low-lift cooling system that potentially offers an increase in HVAC energy performance relative to ASHRAE Standard 90.1-2004.
2010-03-31
UK PubMed Central (United Kingdom)
Dengue virus (DENV) infection is a worsening global health problem. The plaque reduction neutralization test (PRNT) is currently considered to be the “gold standard” to characterize...Full Text Available
2009-11-01
Antiproton production of propagating cosmic rays under distributed reacceleration
Energy Technology Data Exchange (ETDEWEB)
The available measurements on the cosmic-ray antiproton/proton ratio show an excess of antiprotons above predictions derived in the framework of the standard picture of cosmic-ray origin and propagation. Calculations are performed of the production from collisions of cosmic rays with the interstellar gas under the condition of distributed reacceleration. It could be shown that the calculated antiproton/proton ratio is enhanced compared to that derived from the leaky box model, but it remains difficult to bring it into agreement with the data by reasonable astrophysical assumptions. 15 references.
1987-09-01
A novel CFD/structural analysis of a cross parachute
Energy Technology Data Exchange (ETDEWEB)
A novel CFD/structural analysis was performed to predict functionality of a cross parachute under loadings near the structural limits of the parachute. The determination of parachute functionality was based on the computed structural integrity of the canopy and suspension lines. In addition to the standard aerodynamic pressure loading on the canopy, the structural analysis considered the reduction in fabric strength due to the computed aerodynamic heating. The intent was to illustrate the feasibility of such an analysis with the commercially available software PATRAN.
1993-12-31
Test-bed for compact ventilation units; Pruefstand fuer Kompaktlueftungsgeraete fuer Komfortlueftung
Energy Technology Data Exchange (ETDEWEB)
This comprehensive, illustrated report for the Swiss Federal Office of Energy (SFOE) by the University of Applied Sciences in Lucerne, Switzerland takes a look at the testing facility at the university that is used to test compact ventilation systems. These feature heat-recovery and return-air heat-pumps and are used in housing built to low energy-consumption standards such as the Swiss 'Minergie' and 'Minergie-P' standards. The primary goal is a technically comprehensive testing programme for compact ventilation units with heat recovery and heat pumps, which can nevertheless be carried out at reasonable cost. In addition to thermal and flow measurements, acoustic measurements are also carried out. The authors quote that the overall assessment provided can also include service and maintenance, materials used and possible problems with thermal bridges. The test installation is described ...
2005-12-15
Highlights of design and construction of Sendai Nuclear Power Station Unit No.2
International Nuclear Information System (INIS)
As for No.2 plant in Sendai Nuclear Power Station, which is the fourth nuclear power generation facilities in Kyushu Electric Power Co., Inc., all works have been completed, and at present, the final trial operation is under way. In No.2 plant, many new techniques for raising the reliability and safety, improving the maintainability and reducing radiation exposure were introduced on the basis of the operation experience of PWRs obtained so far, similarly to No.1 plant. In this paper, the main items of the new techniques related to the design and construction of the plant are reported. No. 2 plant is a first improved and standardized plant having the thermal output of 2660 MW for standard three-loop PWRs, and the rated power output was set at 890 MW. As for the turbine, TC6F-40 in was adopted. As the improved design, a large reactor containment vessel, 17 x 17 type 9-grid fuel, improved steam generators, a reactor vessel ...
1985-01-01
Future limits on isotropic Lorentz violation in the photon sector from UHECRs and TeV gamma rays
Present and future ultra-high-energy-cosmic-ray facilities (e.g., the Pierre Auger Observatory with South and North components) and TeV-gamma-ray telescope arrays (e.g., HESS/VERITAS and CTA) have the potential to set stringent indirect bounds on the nine Lorentz-violating parameters of nonbirefringent modified Maxwell theory minimally coupled to standard Dirac theory. Theoretically, the most interesting case is isotropic Lorentz violation, which is described by a single parameter [taken to vanish for the case of the standard Lorentz-invariant theory]. It appears possible to obtain in the future an upper (lower) indirect bound on this single isotropic Lorentz-violating parameter at the +10^{-21} (-10^{-17}) level. Comparison is made with existing and future direct bounds from laboratory experiments. The possible physics implications of upper bounds at the 10^{-21} level are also briefly discussed.
2011-01-01
Radioactive waste management in the USSR: A review of unclassified sources. Volume 2
Energy Technology Data Exchange (ETDEWEB)
The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of ...
1991-03-01
Radioactive waste management in the USSR: A review of unclassified sources
Energy Technology Data Exchange (ETDEWEB)
The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of ...
1991-03-01
PROSPECTS AND STATUS OF LOW-ASPECT-RATIO TOKAMAKS
Energy Technology Data Exchange (ETDEWEB)
The prospects for the low-aspect-ratio (A) tokamak to fulfill the requirements of viable fusion power plants are considered relative to the present status in data and modeling. Desirable physics and design features for an attractive Blanket Test Facility and power reactors are estimated for low-A tokamaks based on calculations improved with the latest data from small pioneering experiments. While these experiments have confirmed some of the recent predictions for low-A, they also identify the remaining issues that require verification before reliable projections can be made for these deuterium-tritium applications. The results show that the low-A regime of small size, modest field, and high current offers a path complementary to the standard and high A tokamaks in developing the full potential of fusion power.
1995-01-01
Noise and vibration control offshore towards an improved design procedure
Energy Technology Data Exchange (ETDEWEB)
There is a clear incentive, therefore, for early consideration of the measures required to meet noise and vibration standards. The platform or rig owner and the operator are jointly responsible for agreeing a noise and vibration control policy and approach at the conceptual design stage, and for then passing on their requirements to the engineering design teams. The engineering design teams and acoustic and vibration specialists for their part need to use all their skill and judgement to apply that policy to the intensely complex job of designing and fabricating topsides facilities. With these concerns as background, UEG started, and has nearly completed, a two-phase study to provide detailed guidance to project managers and designers to assist them to develop appropriate policy and procedures and to help them put those procedures into practice. This paper describes the development of UEG's study, its application and benefits.
1983-09-01
Energy Technology Data Exchange (ETDEWEB)
Reliable facility of cyclotron-based real time neutron radiography system has been developed and applied to some industrial components. The equipment for neutron fluoroscopy is based on a sub-compact cyclotron and a LiF/ZnS (Ag) fluorescent screen viewed by a silicon intensifier target TV camera. The real time image is monitored on a CRT, recorded with a standard video recorder and processed by a digital image processor. The effectiveness of our real time neutron radiograph has been demonstrated to be applicable to not only the dynamic observation but also the magnifying and stereoscopic observation of fluoroscopic images.
1987-03-01
National waste terminal storage program. Supplementary quality-assurance requirements
International Nuclear Information System (INIS)
The basic Quality Assurance Program Requirements standard for the National Waste Terminal Storage Program has been developed primarily for nuclear reactors and other fairly well established nuclear facilities. In the case of waste isolation, however, there are many ongoing investigations for which quality assurance practices and requirements have not been well defined. This paper points out these problems which require supplementary requirements. Briefly these are: (1) the language barrier, that is geologists and scientists are not familiar with quality assurance (QA) terminology; (2) earth sciences deal with materials that cannot be characterized as easily as metals or other materials that are reasonably homogeneous; (3) development and control of mathematical models and associated computer programs; (4) research and development.
The NIST/NRL free-electron laser facility
International Nuclear Information System (INIS)
A free-electron laser (FEL) user facility is discussed. The FEL, which will be operated as an oscillator, will be driven by the electron beam of the racetrack microtron (RTM) that is nearing completion. Variation of the electron kinetic energy from 17 MeV to 185 MeV will permit the FEL wavelength to be tuned from 200 nm to 10 #mu#m. Performance will be enhanced by the high brightness, low energy spread, and continuous pulse nature of the RTM electron beam. The authors are designing a new injector to increase the peak current of the RTM. A 3.6-m undulator is under construction, and the 9-m optical cavity is under design. The FEL will emit a continuous train of 3-ps pulses at 66 MHz with an average power of 10--200 W, depending on the wavelength, and a peak power of up to several hundred kW. An experimental area is being prepared with up to five stations for research using the FEL beam.
1989-04-24
Stability and disturbance of large dc superconducting magnets
Energy Technology Data Exchange (ETDEWEB)
This paper addresses the stability aspects of several successful dc superconducting magnets such as large bubble chamber magnets, and magnets for the Mirror Fusion Test Facility and MHD Research Facility. Specifically, it will cover Argonne National Laboratory 12-Foot Bubble Chamber magnets, the 15-foot Bubble Chamber magnets at Fermi National Laboratory, the MFTF-B Magnet System at Lawrence Livermore National Laboratory, the U-25B Bypass MHD Magnet, and the CFFF Superconducting MHD magnet built by Argonne National Laboratory. All of these magnets are cooled in pool-boiling mode. Magnet design is briefly reviewed. Discussed in detail are the adopted stability critera, analyses of stability and disturbance, stability simulation, and the final results of magnet performance and the observed coil disturbances.
1981-11-11
Removal of scattered thermal neutrons using antiscatter grid
International Nuclear Information System (INIS)
One of the significant factors of neutron radiographic image degradation is scattering blur from the object. A practical method is described to enhance image quality by eliminating the overlapping of scattered thermal neutrons component from the objects in ETRR-2 neutron radiography facility, using aluminum Gd-coated antiscatter grid. The MCNP code was used to determine the optimum grid dimensions that will reduce the scattered thermal neutrons from the object. An experiment was performed to determine the optimum grid height and irradiation time that gives the best image with acceptable geometric unsharpness. Using the MCNP code it was found that 97% of the scattered neutrons were removed by the grid. The wall dimensions and Gd coating are so small that the facility resolution cannot detect the image pattern superposition on the film.
2006-12-01
Reflux boiling heat removal in a scaled TMI-2 system test facility
International Nuclear Information System (INIS)
An investigation of decay heat removal by the reflux boiling process was performed on a 1/18 linear-scaled test facility simulating the Three Mile Island (TMI-2) primary system. The objective was to clarify reflux boiling phenomena and core cooling effectiveness. Principal test variables included: core power, primary system water and gas inventories, and steam generator secondary-side coolant flow rate. Of 49 tests conducted, 43 achieved a steady-state heat rejection mode within 3 hours. Subsequent analyses identified two distinct reflux boiling modes. Based upon our current understanding, reflux boiling appears to be an effective process for removing decay heat in a broad range of the conditions investigated for a plant of the TMI configuration.
1980-06-01
Reduction of statistic error in Mihalczo subcriticality measurement
Energy Technology Data Exchange (ETDEWEB)
The theoretical formula for the statistical error estimation in Mihalczo method was derived, and the dependence of the error were investigated on the facility to be measured and on the parameter in the data analysis. The formula was derived based on the reactor noise theory and the error theory for the frequency analysis, and found that the error depends on such parameters as the prompt neutron decay constant, detector efficiencies, and the frequency bandwidth. Statistical errors estimated with the formula was compared with experimental values and verified to be reasonable. Through parameter surveys, it is found that there is an optimum combination of the parameters to reduce the magnitude of the errors. In the experiment performed in DCA subcriticality measurement facility, it is estimated experimentally that the measurement requires 20 minutes to obtain the statistic error of 1% for the keff 0.9. According to the error ...
1998-08-01
Radiological operating experience at FFTF [Fast Flux Test Facility
International Nuclear Information System (INIS)
The Fast Flux Test Facility has been in operation for approximately five years, including about one thousand days of full power operation of the Fast Test Reactor. During that time the collective dose equivalents received by operating personnel have been about two orders of magnitude lower than those typically received at commercial light water reactors. No major contamination problems have been encountered in operating and maintaining the plant, and release of radioactive gas to the environment has been minimal and well below acceptable limits. All shields have performed satisfactorily. Experience to date indicates an apparent radiological superiority of liquid metal reactor systems over current light water plants.
1987-04-22
RELAP5/MOD3.1 and APROS 3.0 analyses of SBLOCA in scaled VVER-440 geometry
Energy Technology Data Exchange (ETDEWEB)
A cold-leg small-break loss-of-coolant accident (SBLOCA) experiment was performed on the PACTEL facility to study the behavior of natural circulation in a VVER-440 reactor geometry. The facility is a volumetrically scaled (1:305) integral test loop simulating the VVER-440 reactors used in Finland. The test results were used to assess the computer codes RELAP5/MOD3.1 and APROS 3.0 for VVER reactors. The behavior of the horizontal steam generator and the effect of the hot-leg loop seal were of particular interest. The specific parameters to be compared included the primary pressure and the downcomer mass flow rate.
1995-12-31
RELAP5/MOD3.1 and APROS 3.0 analyses of SBLOCA in scaled VVER-440 geometry
International Nuclear Information System (INIS)
A cold-leg small-break loss-of-coolant accident (SBLOCA) experiment was performed on the PACTEL facility to study the behavior of natural circulation in a VVER-440 reactor geometry. The facility is a volumetrically scaled (1:305) integral test loop simulating the VVER-440 reactors used in Finland. The test results were used to assess the computer codes RELAP5/MOD3.1 and APROS 3.0 for VVER reactors. The behavior of the horizontal steam generator and the effect of the hot-leg loop seal were of particular interest. The specific parameters to be compared included the primary pressure and the downcomer mass flow rate.
1995-11-01
Energy Technology Data Exchange (ETDEWEB)
The Hazardous Materials Control Module (HMC) is one module of four for the Industrial Health component. The HMC module was designed to inform employees of health and safety hazards in the workplace and to track the movement of hazardous materials through the facility. The module performs these functions by maintaining health and safety data on hazardous materials used in the facility, and by tracking who requests information about any hazardous materials. The HMC module gets its information from two sources. The first one is the Hazardous Materials Information System (HMIS), this is a national system that is used by the Department of Defense. It is loaded on to the system via tapes that contain all safety, health and transportation information about a particular product. The second is Material Safety Data Sheets (MSDS) that are procured by a particular site. This information is manually entered into their own personal ...
1987-01-16
Five years operating experience at the Fast Flux Test Facility
Energy Technology Data Exchange (ETDEWEB)
The Fast Flux Test Facility (FFTF) is a 400 Mw(t), loop-type, sodium-cooled, fast neutron reactor. It is operated by the Westinghouse Hanford Company for the United States Department of Energy at Richland, Washington. The FFTF is a multipurpose test reactor used to irradiate fuels and materials for programs such as Liquid Metal Reactor (LMR) research, fusion research, space power systems, isotope production and international research. FFTF is also used for testing concepts to be used in Advanced Reactors which will be designed to maximize passive safety features and not require complex shutdown systems to assure safe shutdown and heat removal. The FFTF also provides experience in the operation and maintenance of a reactor having prototypic components and systems typical of large LMR (LMFBR) power plants. The 5 year operational performance of the FFTF reactor is discussed in this report. 6 refs., 10 figs., 2 tabs.
1987-04-01
Five years operating experience at the Fast Flux Test Facility
International Nuclear Information System (INIS)
The Fast Flux Test Facility (FFTF) is a 400 Mw(t), loop-type, sodium-cooled, fast neutron reactor. It is operated by the Westinghouse Hanford Company for the United States Department of Energy at Richland, Washington. The FFTF is a multipurpose test reactor used to irradiate fuels and materials for programs such as Liquid Metal Reactor (LMR) research, fusion research, space power systems, isotope production and international research. FFTF is also used for testing concepts to be used in Advanced Reactors which will be designed to maximize passive safety features and not require complex shutdown systems to assure safe shutdown and heat removal. The FFTF also provides experience in the operation and maintenance of a reactor having prototypic components and systems typical of large LMR (LMFBR) power plants. The 5 year operational performance of the FFTF reactor is discussed in this report. 6 refs., 10 figs., 2 tabs.
1987-09-13
Mercury flow experiments. 3. Simulation test plan under abnormal condition
Energy Technology Data Exchange (ETDEWEB)
Japan Atomic Energy Research Institute (JAERI) and High Energy Accelerator Research Organization (KEK) are promoting construction plan of Material-Life Science Facility, which is consisted of Muon Science Facility and Neutron Scattering Facility, in order to open up the new science fields. The Neutron Scattering Facility will be utilized for advanced fields of Material and Life science using high intensity neutrons generated by the spallation reaction induced by injecting a 1 MW pulsed proton beam onto a mercury target. Design of the spallation mercury target system is in progress to obtain good neutron performance keeping high reliability and safety. The target material is mercury. As a result of the spallation reaction, large amount of radioactive spallation products are to be contained in the mercury. Therefore to establish the safety of the target system, transient behaviors of ...
2002-02-01
International Nuclear Information System (INIS)
The US Department of Energy has provided support to four universities and the Oak Ridge National Laboratory in order to pursue research leading to the development and deployment of an advanced robotic system capable of performing tasks that are hazardous to humans, that generate significant occupational radiation exposure, and/or whose execution times can be reduced if performed by an automated system. The goal is to develop a generation of advanced robotic systems capable of performing surveillance, maintenance, and repair tasks in nuclear facilities and other hazardous environments. This goal will be achieved through a team effort among the Universities of Florida, Michigan, Tennessee, Texas, and the Oak Ridge National Laboratory, and their industrial partners, Combustion Engineering, Martin Marietta Baltimore Aerospace, Odetics, Remotec, and Telerobotics International. Each of the universities and ...
Transient performance of FFTF [Fast Flux Test Facility] reference fuel
International Nuclear Information System (INIS)
Fourteen irradiated Fast Flux Test Facility (FFTF) fuel pins were subjected to representative overpower transients in six flowing sodium loop experiments conducted in the TREAT reactor. The transient tests were extended to substantial overpower levels well beyond protected levels, with some tests intentionally run to failure to identify failure thresholds and characteristics. Test variables included transient ramp rate (5, 50, and 100 cents/s) and burnup (2 to 58 MWd/kg). Performance limits and failure characteristics were identified, and cladding strain and fuel melting data were obtained for development and verification of transient analysis codes. The test results demonstrated that FFTF Reference fuel pins are capable of surviving overpower levels well beyond the FFTF secondary Plant Protection System (PPS) trip limit of 1.25 times normal rated power. Based on analytical evaluations to interpolate and extrapolate test results to the full ...
1986-09-07
Performance Assessment of Physical Protection System at Wolsong Nuclear Power Plant using SAVI code
Energy Technology Data Exchange (ETDEWEB)
The 9/11 event in the U.S.A has increased international terror possibilities against nuclear facilities including nuclear power plants(NPPs). It is necessary to assess the performance of existing physical protection system(PPS) at nuclear facilities based on such malevolent acts. A PPS is a complex configuration of detection, delay, and response elements. Several techniques are available to analyze a PPS and evaluate its effectiveness. Sandia National Laboratory(SNL) in the USA was developed a System Analysis of Vulnerability to Intrusion (SAVI) computer code for this purpose. It is powerful software for evaluating the effectiveness of PPS against outsider threats. This study presents the performance assessment of the PPS at Wolsong NPP using SAVI code. The first is that the SAVI constructs the site-specific Adversary Sequence Diagram (ASD) of the PPS. This provides a methods of graphically representing ...
2005-07-01
Data report of BWR post-CHF tests. Transient core thermal-hydraulic test program. Contract research
Energy Technology Data Exchange (ETDEWEB)
JAERI has been performing transient core thermal-hydraulic test program. In the program, authors performed BWR/ABWR DBE simulation tests with a test facility, which can simulate BWR/ABWR transients. The test facility has a 4 x 4 bundle core simulator with 15-rod heaters and one non-heated rod. Through the tests, authors quantified the thermal safety margin for core cooling. In order to quantify the thermal safety margin, authors collected experimental data on post-CHF. The data are essential for the evaluation of clad temperature transient when core heat-up occurs during DBEs. In comparison with previous post-CHF tests, present experiments were performed in much wider experimental condition, covering high clad temperature, low to high pressure and low to high mass flux. Further, data at wider elevation (lower to higher elevation of core) were obtained in the present experiments, ...
2001-03-01
Energy Technology Data Exchange (ETDEWEB)
The objective of this research project is to demonstrate sensing, communication, information and control technologies to achieve a seamless integration of multivendor distributed energy resource (DER) units at aggregation levels that meet individual user requirements for facility operations (residential, commercial, industrial, manufacturing, etc.) and further serve as resource options for electric and natural gas utilities. The fully demonstrated DER aggregation system with embodiment of communication and control technologies will lead to real-time, interactive, customer-managed service networks to achieve greater customer value. Work on this Advanced Communication and Control Project (ACCP) consists of a two-phase approach for an integrated demonstration of communication and control technologies to achieve a seamless integration of DER units to reach progressive levels of aggregated power output. Phase I involved design and proof-of-design, and Phase II involves ...
2008-09-30
SP-100 fuel pin performance: Results from irradiation testing
Energy Technology Data Exchange (ETDEWEB)
A total of 86 experimental fuel pins with various fuel, liner, and cladding candidate materials have been irradiated in the Experimental Breeder Reactor-II (EBR-II) and the Fast Flux Test Facility (FFTF) reactor as part of the SP-100 fuel pin irradiation testing program. Postirradiation examination results from these fuel pin are key in establishing performance correlations and demonstrating the lifetime and safety of the reactor fuel system. This paper provides a brief description of the in-reactor fuel pin tests and presents the most recent irradiation data on the performance of wrought rhenium (Re) liner material and high density UN fuel at goal burnup of 6 atom percent (at. %). It also provides an overview of the significant variety of other fuel/liner/cladding combinations which were irradiated as part of this program and which may be of interest to more advanced efforts.
1993-09-01
Development of fission Mo-99 production technology
Energy Technology Data Exchange (ETDEWEB)
This R and D project is planed to supply domestic demands of Mo-99 through fission route, and consequently this project will be expected to rise up utilization of HANARO and KAERI's capability for marketing extension into domestic and oversea radiopharmaceutical market. HEU and LEU target types are decided and designed for fission Mo-99 production in domestic. Experimental study of target fabrication technology was performed and developed processing equipments. And conceptual design of target loading/unloading in/from HANARO device are performed. Tracer test of Mo-99 separation and purification process was performed, test results reach to Mo-99 recovery yield above 80% and decontamination factor above 1600. Combined Mo-99 separation and purification process was decided for hot test scheduled from next year, and performance test was performed. Conceptual design for ...
2001-05-01
The Wilsonville Advanced Coal Liquefaction Research and Development Facility, Wilsonville, Alabama
The investigation of various Two-Stage Liquefaction (TSL) process configurations was conducted at the Wilsonville Advanced Coal Liquefaction R D Facility between July 1982 and September 1986. The facility combines three process units. There are the liquefaction unit, either thermal (TLU) or catalytic, for the dissolution of coal, the Critical Solvent Deashing unit (CSD) for the separation of ash and undissolved coal, and a catalytic hydrogenation unit (HTR) for product upgrading and recycle process solvent replenishment. The various TSL process configurations were created by changing the process sequence of these three units and by recycling hydrotreated solvents between the units. This report presents a description of the TSL configurations investigated and an analysis of the operating and performance data from the period of study. Illinois No. 6 Burning Star Mine coal Wyodak Clovis Point Mine coal were processed. ...
1990-05-01
One-piece removal of JRR-3 reactor block
Energy Technology Data Exchange (ETDEWEB)
JRR-3 is a research reactor of 10 MWt output, which attained the criticality in 1962. All the design, manufacture, installation and others of this reactor were carried out by Japanese technologies, except the fuel and heavy water as the moderator and coolant, therefore it is nicknamed Home-made No.1 Reactor. Recently, due to the change in the state of utilizing research reactors and the rise of quality in the utilization, JRR-3 has become to be unable to meet sufficiently the needs of users. The plan of reconstructing the JRR-3 was considered under such situation, and in order to reuse the reactor building, the reactor proper is removed, and an entirely new, high performance, versatile reactor is to be constructed. In this paper, as to the removal works of the JRR-3 reactor proper, the method of execution, design, the execution of works and so on are outlined. The removal works of the reactor facilities were started in February, 1986. The ...
1987-07-01
New developments in dry spent fuel storage
International Nuclear Information System (INIS)
As shown in various new examples, HABOG facility (Netherlands), CERNAVODA (Candu - Romania), KOZLODUY (WWER - Bulgaria), CHERNOBYL ( RMBK - Ukraine), MAYAK (Spent Fuel from submarine and Icebreakers - Russia), recent studies allow to confirm the flexibility and performances of the CASCAD system proposed by SGN, both in safety and operability, for the dry storage of main kinds of spent fuel. The main features are: A multiple containment barrier system: as required by international regulation, 2 independent barriers are provided (tight canister and storage pit); Passive cooling, while the Fuel Assemblies are stored in an inert atmosphere and under conditions of temperature preventing from degradation of rod cladding; Sub-criticality controlled by adequate arrangements in any conditions; Safe facility meeting ICPR 60 Requirements as well as all applicable regulations (including severe weather conditions and earthquake); Safe ...
2001-06-18
Materials performance at the Wilsonville Coal Liquefaction Facility, 1989--1991
The Advanced Coal Liquefaction Research and Development Facility in Wilsonville, Alabama, is funded by the US Department of Energy (DOE), the Electric Power Research Institute (EPRI), and Amoco Corporation. On behalf of these organizations, Southern Company Services manages and Southern Clean Fuels Division of Southern Electric International operates the Wilsonville facility. Oak Ridge National Laboratory (ORNL) receives funding from DOE to provide materials technical support to the Wilsonville operators. For the period July 1987 through November 1990 the plant was operated with two reactors a thermal reactor and a catalytic reactor in a close-coupled integrated two-stage liquefaction mode. Coal processed was obtained from several seams including Ohio No. 6, Illinois No. 6, and Pittsburgh No. 8, as well as Texas lignite and several subbituminous coals. Corrosion samples which were removed for examination at the end of this period were exposed ...
1991-01-01
Energy Technology Data Exchange (ETDEWEB)
The EMP consists of a Compliance Monitoring Sampling Program and a Supplemental monitoring Sampling Program. The Compliance Monitoring Sampling Program will be conducted during a summer and a winter Baseline periods during the Pre-Construction/Construction phases of the Project and during a summer and a winter period following the successful Startup and Operational phase of the completed Project. compliance monitoring consist of conducting all the sampling and observation programs associated with existing required Federal, State, and Local Regulations, Permits and Orders. These include air, water, and waste monitoring and OSHA and NESHAP monitoring. The Supplemental Monitoring Program will also be conducted during a summer and a winter Baseline periods during the Pre-Construction/Construction phases of the Demonstration Facility and during a summer and a winter period following the successful startup and Operational phase of the completed ...
1992-09-21
Innovative coke oven gas cleaning system for retrofit applications
Energy Technology Data Exchange (ETDEWEB)
The EMP consists of a Compliance Monitoring Sampling Program and a Supplemental monitoring Sampling Program. The Compliance Monitoring Sampling Program will be conducted during a summer and a winter Baseline periods during the Pre-Construction/Construction phases of the Project and during a summer and a winter period following the successful Startup and Operational phase of the completed Project. compliance monitoring consist of conducting all the sampling and observation programs associated with existing required Federal, State, and Local Regulations, Permits and Orders. These include air, water, and waste monitoring and OSHA and NESHAP monitoring. The Supplemental Monitoring Program will also be conducted during a summer and a winter Baseline periods during the Pre-Construction/Construction phases of the Demonstration Facility and during a summer and a winter period following the successful startup and Operational phase of the completed ...
1992-09-21
Experiments with the HORUS-II test facility
Energy Technology Data Exchange (ETDEWEB)
Within the scope of the German reactor safety research the thermohydraulic computer code ATHLET which was developed for accident analyses of western nuclear power plants is more and more used for the accident analysis of VVER-plants particularly for VVER-440,V-213. The experiments with the HORUS-facilities and the analyses with the ATHLET-code have been realized at the Technical University Zittau/Goerlitz since 1991. The aim of the investigations was to improve and verify the condensation model particularly the correlations for the calculation of the heat transfer coefficients in the ATHLET-code for pure steam and steam-noncondensing gas mixtures in horizontal tubes. About 130 condensation experiments have been performed at the HORUS-II facility. The experiments have been carried out with pure steam as well as with noncondensing gas injections into the steam mass flow. The experimental simulations are characterized as ...
1997-12-31
European facilities for accelerator neutrino physics: perspectives for the decade to come
Very soon a new generation of reactor and accelerator neutrino oscillation experiments - Double Chooz, Daya Bay, Reno and T2K - will seek for oscillation signals generated by the mixing parameter theta_13. The knowledge of this angle is a fundamental milestone to optimize further experiments aimed at detecting CP violation in the neutrino sector. Leptonic CP violation is a key phenomenon that has profound implications in particle physics and cosmology but it is clearly out of reach for the aforementioned experiments. Since late 90's, a world-wide activity is in progress to design facilities that can access CP violation in neutrino oscillation and perform high precision measurements of the lepton counterpart of the Cabibbo-Kobayashi-Maskawa matrix. In this paper the status of these studies will be summarized, focusing on the options that are best suited to exploit existing European facilities (firstly CERN and the INFN Gran ...
2009-01-01
Energy Technology Data Exchange (ETDEWEB)
In this report, the descriptions of the DIVA test facility and those test matrixes are presented. The test sections simulate the downcomer annulus of DVI system with various scalling methodologies. The UPTF one has 1/7.5 scale and the APR-1400 test sections are reduced in 1/7 scale and 1/5 scale respectively. Also, the instrumentations, measuring methods are described. The major measuring parameters are ECC injection rate, air injection rate, bypass fraction, system pressure and so on. And finally, the operation procedure and experimental steps are introduced. From the DIVA tests, the multi-dimensional behaviors of two-phase flow in the downcomer during the reflood phase can be investigated using a transparent test facility. Also comparing the experimental data which are performed in various scale downcomer, it is expected that some criteria of scalling methodology proper to the DVI system can be derived. 10 refs., 19 ...
2002-03-01
A consortium of four institutions, based at Western Michigan University, was to plan a Research and Development Center on Student Testing, Evaluation, and Standards Setting. The four consortium sites are Boston College, the Dallas Independent School District, the University of Kansas, and Western Michigan University. This report is a final performance report for the planning grant made to Western Michigan University by the National Institute of Education. The first section provides a summary of the planning activities actually conducted under the grant. It includes a description of particular problems and successes, a list of participants and their affiliations, and an evaluation report for the planning project. The second section is a technical report on the Research and Development (R and D) mission for the Center. It updates the mission and strategy statement contained in the planning grant application and includes an agenda, with ...
1985-09-01
Photovoltaic performance and reliability workshop
Energy Technology Data Exchange (ETDEWEB)
This proceedings is the compilation of papers presented at the ninth PV Performance and Reliability Workshop held at the Sheraton Denver West Hotel on September 4--6, 1996. This years workshop included presentations from 25 speakers and had over 100 attendees. All of the presentations that were given are included in this proceedings. Topics of the papers included: defining service lifetime and developing models for PV module lifetime; examining and determining failure and degradation mechanisms in PV modules; combining IEEE/IEC/UL testing procedures; AC module performance and reliability testing; inverter reliability/qualification testing; standardization of utility interconnect requirements for PV systems; need activities to separate variables by testing individual components of PV systems (e.g. cells, modules, batteries, inverters,charge controllers) for individual reliability and then test them in actual system ...
1996-10-01
Performance testing of selected types of electronic personal dosimeters used in Sudan
International Nuclear Information System (INIS)
Measurements were carried out for calibration and performance testing of a set of 10 electronic personal dosimeters (EPDs) at the Secondary Standard Dosimetry Laboratory of Sudan. Calibrations were carried out at three X-ray beam qualities described in ISO standard 4037 in addition to 137Cs and 60Co gamma ray beams. The experimental was performed with EPDs mounted on ICRU Slab phantom. X-ray and ?-ray beams were characterized in terms of air kerma free-in-air which were converted to the known delivered personal dose equivalent, Hp(10) using appropriate the air kerma to personal dose equivalent conversion coefficients. Dosimeters tested showed excellent energy and angular response and relative error of indication within the recommended limit for photon energies from 65 keV to 1.25 MeV. The study showed encouraging results for using electronic dosimeters in personal dosimetry.
2010-12-01
Evaluating technologies for tactical information management in net-centric systems
Recent trends in distributed real-time and embedded (DRE) systems motivate the development of tactical information management capabilities that ensure the right information is delivered to the right place at the right time to satisfy quality of service (QoS) requirements in heterogeneous environments. A promising approach to building and evolving large-scale and long-lived tactical information management systems are standards-based QoS-enabled publish/subscribe (pub/sub) platforms that enable applications to communicate by publishing information they have and subscribing to information they need in a timely manner. Since there is little existing evaluation of how well these platforms meet the performance needs of tactical information management, this paper provides two contributions: (1) it describes three common architectures for the OMG Data Distribution Service (DDS), which is a QoS-enabled pub/sub platform standard, and ...
2007-05-01
Analysis of free electron laser performance utilizing the National Bureau of Standards' CW microtron
International Nuclear Information System (INIS)
The National Bureau of Standards' (NBS) CW racetrack microtron (RTM) will be utilized as a driver for a free electron laser (FEL) oscillator. The NBS RTM possesses many exceptional properties of value for the FEL: i) CW operation, ii) energy from 20-185 MeV, iii) small energy spread and emittance, iv) excellent energy stability, and v) high average power. The 1-D FEL gain formula predicts that the FEL would oscillate at the fundamental approximately from 0.25 #mu#m to 10 #mu#m when up-grading the peak current to #>=# 2 A. In this paper, the authors present 3-D self-consistent numerical results including several realistic effects, such as emittance, betatron oscillations, diffraction and refraction. The results indicate that the design value of the transverse emittance is small enough that it does not degrade the FEL performance for intermediate to long wavelengths, and only slightly degrades the performance at the ...
A Human reliability analysis of post-accident human errors in the PSA of KSNP
International Nuclear Information System (INIS)
Korea Atomic Energy Research Institute, using the ASME PRA Standard, evaluated the PSA model of the Korea Standard Nuclear Power Plant (KSNP) and identified the items to be improved to enhance its quality. The new risk monitor PSA model for the KSNP of which quality was enhanced is called as PRiME-U3i. The evaluation results of human reliability analysis (HRA) of the post-accident human errors in the PSA model of the KSNP showed that 10 items among 19 items of supporting requirements for those in the ASME PRA Standard were identified as them to be improved. Thus, we newly carried out a HRA for post-accident human errors for the KSNP PSA model as the target of grading its quality above ASME PRA Standard Category I+. Following tasks were additionally major tasks performed in the HRA of post-accident human errors of PRiME-U3i compared with the previous PSA model of the KSNP: interviews ...
2004-10-28
Geothermal heat cycle research: Supercritical cycle with horizontal counterflow condenser
Energy Technology Data Exchange (ETDEWEB)
The Heat Cycle Research Program, which is being conducted for the Department of Energy, has as its objective the development of the technology for effecting the improved utilization of moderate temperature geothermal resources. To meet this objective, the program has as one of its goals to improve the performance of geothermal binary cycles to levels approaching the practicable thermodynamic maximum. In pursuit of this goal, tests are being conducted at the Heat Cycle Research Facility located at the DOE Geothermal Test Facility, East Mesa, California. The current testing involves the investigation of binary power cycle performance utilizing mixtures of non-adjacent hydrocarbons as the working fluids, with supercritical vaporization and in-tube condensation of the working fluid. In addition to the present test program, preparations are being made to investigate the binary cycle ...
1987-01-01
International Nuclear Information System (INIS)
This standard provides requirements and guidelines for installation, inspection and testing activities that assure the quality of important mechanical parts of a nuclear power plant not covered by the ASME Boiler and Pressure Vessel Code, Section III, during construction. These parts include those mechanical systems and components whose satisfactory performance is required: for the plant to operate reliably; to prevent accidents that could cause undue risk to the health and safety of the public; or to mitigate the consequences of such accidents if they were to occur. The requirements of this standard deal with the protection and control necessary to assure that the requisite quality of those important parts of the plant are preserved from the time items are removed from storage or receiving until they are incorporated into the plant up to but not including fuel loading for PWR plants and the completion of cold functional ...
Probing anomalous top-quark couplings induced by dim.6 operators at photon colliders
Energy Technology Data Exchange (ETDEWEB)
Possible anomalous top-quark couplings induced by SU(2)xU(1) gauge-invariant dimension-6 effective operators were studied in the process of ttbar productions and decays at polarized {gamma}{gamma} colliders. Two CP-violating asymmetries, a linear-polarization asymmetry and a circular-polarization asymmetry, were computed including both non-standard ttbar{gamma} and {gamma}{gamma}H couplings. An optimal-observable analysis for the process {gamma}{gamma}{yields}ttbar{yields}l{sup {+-}} was performed in order to estimate the precision for determination of all relevant non-standard couplings, including the anomalous tbW coupling.
2004-06-21
Evaluation technique of neutron-irradiation embrittlement in welded RPV
International Nuclear Information System (INIS)
The ductile-brittle transition behavior of neutron-irradiated welded A533B C1.1 steel has been studied by means of small specimen test technique for discussing the specimen size effects on the impact properties. Standard size, one-third size and 1.5 mm size Charpy V-notch specimens were prepared. Neutron irradiation was performed in JMTR with fluencies up to 0.75 and 1.3x10"2"4 n/m"2 (E > 1 MeV). Normalization of the USE is done by a curve fitting method and the USE of different size of specimens can be expressed by the equation; E=a x B"n, where a is a constant and n is an exponent. There observed linear relationships between DBTTs obtained using standard and sub-sized specimens. (author)
2006-07-01
British Library Electronic Table of Contents (United Kingdom)
Phenytoin (PHT), phenobarbital (PHB), lamotrigine (LTG), and topiramate (TPM) are some of the most widely used antiepileptic drugs (AEDs). Monitoring of their concentrations in serum is important for the treatment of epilepsy. A reference measurement procedure (RMP) for certification of PHT, PHB, LTG, and TPM in serum has been developed and critically evaluated. Isotopically labeled compounds of PHT, PHB, LTG, and TPM are used as internal standards for the four AEDs. The four drugs and their respective labeled internal standards are simultaneously extracted from serum using solid-phase extraction prior to reversed-phase liquid chromatography?tandem mass spectrometry (LC-MS/MS). Chromatographic separation was performed using a C18 column. Electrospray ionization (ESI) in the positive ion mo...
2011-01-01
Energy Technology Data Exchange (ETDEWEB)
This project seeks to produce sufficient information on the physical and chemical nature of Coolside waste to design and construct physically stable and environmentally safe landfills. Unconfined compressive strength and permeability tests are reported on samples remolded near 90, 95, and 100% of low energy, standard, and modified dry densities. Unconfined compressive strength tests were also performed on some of the samples after permeability tests were completed. Swell tests were initiated on samples from Coolside pilot plant run {number_sign}2 and on a FBC hydrated ash remolded near 95% of standard density and optimum moisture content.
1993-11-01
Continuous emission monitoring and quality assurance requirements for new power plants
International Nuclear Information System (INIS)
Electric utility plants, for which construction commenced after September 18, 1978, must install and operate continuous emission monitoring (CEM) systems to demonstrate compliance with SO_2 and NO_x emission standards. Furthermore, effective December 4, 1987, each plant must develop and implement a CEM quality assurance (QA) program. This paper reviews the CEM and QA requirements set forth by new source performance standards (NSPS) promulgated by the Environmental Protection Agency. The paper summarizes operating characteristics of the 32 power plants currently subject to NSPS and describes the types of CEM systems used by these plants. Also, to the extent available, the paper presents the results of initial (i.e., first quarter 1988) QA activities (e.g., audits and calibration drift assessments) conducted by these plants.
1988-09-25
Energy Technology Data Exchange (ETDEWEB)
The aim of this study is to develop the methodology which enables to identify the mechanical properties of element such as stress intensity factor by using the AE parameters. Considering the multivariate and nonlinear properties of AE parameters such as ringdown count, rise time, energy, event duration and peak amplitude from fatigue cracks of machine element the principal component regression(PCR) and artificial neural network(ANN) models for the estimation of stress intensity factor were developed and validated. The AE parameters were found to be very significant to estimate the stress intensity factor. Since the statistical values including correlation coefficients, standard mr of calibration, standard error of prediction and bias were stable, the PCR and ANN models for stress intensity factor were very robust. The performance of ANN model for unknown data of stress intensity factor was better than that of PCR model
2001-02-15
A simplified method for cholesterol determination in meat and meat products
British Library Electronic Table of Contents (United Kingdom)
The objectives of this study were to develop an accurate and precise method for cholesterol quantification in meat samples based on modifications made to an existing procedure (AOAC Official Method 994.10), and to apply this modified method to evaluate cholesterol levels in longissimus muscles (LM) from Angus (AN, n=5), Brahman (BR, n=4), and Romosinuano (RM, n=9) breeds. Validation of this method was performed using a meat homogenate (Standard Reference Material 1546) from National Institute of Standards and Technology (NIST), and LM samples from the three breeds with fat contents ranging from 2.4% to 9.3%. The results indicated that the modified method was accurate with cholesterol recovery exceeding 95%. The method was also found to be precise with an average coefficient of variation of...
2008-01-01
British Library Electronic Table of Contents (United Kingdom)
Background Laparoscopic inguinal hernia repair has been around since the 1990s. A novel surgical approach known as laparoendoscopic single-site surgery (LESS) has been developed to reduce the port-related morbidities and improve the cosmetic outcomes of laparoscopic surgery, including totally extraperitoneal (TEP) inguinal hernia repair. The aim of the present study was to evaluate the safety and feasibility of the LESS TEP technique for inguinal hernia repair and compare the outcomes with the standard TEP approach. Methods Between January and May 2009, 54 consecutive healthy patients (48 men and 6 women) underwent LESS TEP inguinal hernia repair at our institute. All procedures were performed using our homemade single port for simultaneous passage of the laparoscope and instruments. The p...
2011-01-01
Energy Technology Data Exchange (ETDEWEB)
Documentation and use of various economic analysis tools, especially the SOLFIN 2, KRUNCH, LSAP, and SIPP computer programs, are provided. The report deals with the use of these tools to perform the social economic analysis which underlies building standards. A brief description of life-cycle cost methodology is presented. The documentation of SOLFIN 2 is included. Description of first cost calculations and life-cycle cost sensitivity analysis are given. A detailed account of the general description of how electricity costs are calculated is given in an appendix. Program listings for KRUNCH, SIPP, and LSAP are given in Appendix B. Fuel costs for low, medium, and high conservation scenarios are presented in Appendix C. (MCW)
1982-03-01
Energy Technology Data Exchange (ETDEWEB)
Before disposing of transuranic radioactive wastes in the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with applicable long-term regulations of the United States Environmental Protection Agency (EPA). Sandia National Laboratories is conducting iterative performance assessments of the WIPP for the DOE to provide interim guidance while preparing for final compliance evaluations. This volume contains an overview of WIPP performance assessment and a preliminary comparison with the long-term requirements of the Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191, Subpart B).
1992-12-01
Hardware Virtualization Support In INTEL, AMD And IBM Power Processors
At present, the mostly used and developed mechanism is hardware virtualization which provides a common platform to run multiple operating systems and applications in independent partitions. More precisely, it is all about resource virtualization as the term hardware virtualization is emphasized. In this paper, the aim is to find out the advantages and limitations of current virtualization techniques, analyze their cost and performance and also depict which forthcoming hardware virtualization techniques will able to provide efficient solutions for multiprocessor operating systems. This is done by making a methodical literature survey and statistical analysis of the benchmark reports provided by SPEC (Standard Performance Evaluation Corporation) and TPC (Transaction processing Performance Council). Finally, this paper presents the current aspects of hardware virtualization which will help the IT managers ...
2009-01-01
Gas Appliance Technology Center: Annual report, January-December 1986
Energy Technology Data Exchange (ETDEWEB)
The report reviews the activity during the fourth year of Gas Research Institute's Gas Appliance Technology Center program. Work on gas appliances involved a conceptual table-top multi-function oven, development of an indirect-fired conveyor oven, and performance comparisons of smooth cooktops. Performance-evaluation methods for commercial ovens were evaluated. Design improvements were made to a direct-fired conveyor oven and a pulse-combustion deep-fat fryer. Performance of common vents were studied, and a device was designed to allow incorporation of appliances with positive vent pressures into such systems. Standards-related work included draft-hood capacities, flexible corrugated-connector corrosion, and sediment trap efficiencies. Heating-related work comprised conceptual design of a vented baseboard heater and a centralized heat-transfer fluid system.
1987-08-01
Experience in complying with quality assurance requirements for cask lifting devices
International Nuclear Information System (INIS)
The Nuclear Assurance Corporation (NAC) owns and operates four NAC-1 truck casks. These casks are used to ship spent reactor fuel assemblies and radioactive reactor-core components. The casks have been loaded or unloaded at a total of fifteen nuclear facilities in the United States. In addition, NAC has used another large, overweight-truck cask to ship radioactive reactor core components from a reactor to a waste burial site. There are many individual differences in the cask handling facilities at each of the reactor stations, nuclear research facilities and the storage and burial sites serviced. Various types of auxiliary lifting and handling devices for on-site cask operations have been required. The quality assurance requirements for the equipment used in interfacing casks with nuclear power plant facilities have become more stringent. This paper presents details on the type of special equipment ...
Energy Technology Data Exchange (ETDEWEB)
During third quarter 1994, samples from AMB groundwater monitoring wells at the Metallurgical Laboratory Hazardous Waste Management Facility (Met Lab HWMF) were analyzed for selected heavy metals, indicator parameters, radionuclides, volatile organic compounds, and other constituents. Eight parameters exceeded standards during the quarter. As in previous quarters, tetrachloroethylene and trichloroethylene exceeded final Primary Drinking Water Standards (PDWS). Bis(2-ethylhexyl) phthalate exceeded final PDWS in one well. Aluminum, iron, manganese, tin, and total organic halogens exceeded the Savannah River Site (SRS) Flag 2 criteria. Groundwater flow direction and rate in the M-Area Aquifer Zone were similar to previous quarters. Conditions affecting determination of groundwater flow directions and rates in the Upper Lost Lake Aquifer Zone, Lower Lost Lake Aquifer Zone, and the Middle Sand Aquifer Zone of the Crouch Branch ...
1994-12-01
Energy Technology Data Exchange (ETDEWEB)
A method for determining the reactivity of highly subcritical systems of fissile material, using neutron-noise power spectral densities in conjunction with a /sup 252/Cf source, had previousy been tested in two fast reactor critical assemblies (a mockup of the Fast Flux Test Facility reactor and unreflected enriched uranium metal assemblies) and one thermal reactor (a light-water moderated and reflected lattice of Oak Ridge Research Reactor fuel elements). The last-mentioned test demonstrated the effectiveness of the method in water-moderated systems and thereby prompted the present study of its application to facilities for fuel preparation, reprocessing, and storage. To investigate the applicability of this method to facilities for fuel preparation, reprocessing, and storage, limited experiments were performed with a uranyl fluoride solution. The Los Alamos National Laboratory SHEBA ...
1981-01-01
Performance of the upgraded LTP-II at the ALS Optical Metrology Laboratory
Energy Technology Data Exchange (ETDEWEB)
The next generation of synchrotrons and free electron laser facilities requires x-ray optical systems with extremely high performance, generally of diffraction limited quality. Fabrication and use of such optics requires adequate, highly accurate metrology and dedicated instrumentation. Previously, we suggested ways to improve the performance of the Long Trace Profiler (LTP), a slope measuring instrument widely used to characterize x-ray optics at long spatial wavelengths. The main way is use of a CCD detector and corresponding technique for calibration of photo-response non-uniformity [J. L. Kirschman, et al., Proceedings of SPIE 6704, 67040J (2007)]. The present work focuses on the performance and characteristics of the upgraded LTP-II at the ALS Optical Metrology Laboratory. This includes a review of the overall aspects of the design, control system, the movement and measurement regimes for the ...
2008-07-14
Energy Technology Data Exchange (ETDEWEB)
The German voluntary standard 'Passivhaus' (passive house) leads to buildings with practically no energy consumption. The first residential buildings of this type were built in 1998 and the first tertiary buildings in 2000. Such a passive house must fulfill 5 efficiency criteria: annual space heating needs {<=} 15 kWh/m{sup 2}, U{sub v} envelope coefficient lower than 0.15 W/(m{sup 2}.K), U{sub v} of openings lower than 0.8 W/(m{sup 2}.K), airtightness {<=} 0.6 volume/hour, and total energy needs (space heating, hot water, ventilation, lighting and domestic uses) measured at the meter lower than 42 kWh/m{sup 2}.year. This article makes a status of the effective efficiency of existing passive buildings both in the residential and tertiary sectors and presents some possible ways of improvement. (J.S.)
2005-10-01
Energy Technology Data Exchange (ETDEWEB)
The Natural Gas Vehicle Challenge `92, organized by Argonne National Laboratory and sponsored by the US Department of Energy, the Energy, Mines, and Resources - Canada, the Society of Automotive Engineers, and many others, resulted in 20 varied approaches to the conversion of a gasoline-fueled, spark-ignited, internal combustion engine to dedicated natural gas use. Starting with a GMC Sierra 2500 pickup truck, donated by General Motors, teams of college and university student engineers strived to optimize Chevrolet V-8 engines operating on natural gas for improved emissions, fuel economy, performance, and advanced design features. This paper focuses on the results of the emission event, and compares engine mechanical configurations, engine management systems, catalyst configurations and locations, and approaches to fuel control and the relationship of these parameters to engine-out and tailpipe emissions of regulated exhaust constituents. Nine of the ...
1992-09-01
Using Zgamma candidate events collected by the CDF detector at the Tevatron Collider, we search for potential anomalous (non-standard-model) couplings between the Z boson and the photon. At the hard scatter energies typical of the Tevatron, standard model Zgamma couplings are too weak to be detected by current experiments; hence any evidence of couplings indicates new physics. Measurements are performed using data corresponding to an integrated luminosity of 4.9 /fb in the Z -> nunubar decay channel and 5.1 /fb in the Z -> l^+l^- (l=mu, e) decay channels. The combination of these measurements provides the most stringent limits to date on Zgamma trilinear gauge couplings. Using an energy scale of Lambda = 1.5 TeV to allow for a direct comparison with previous measurements, we find limits on the CP-conserving parameters that describe Zgamma couplings to be |h_3^{\\gamma,Z}| < 0.017 and |h_4^{\\gamma,Z}| < 0.0006. ...
2011-01-01
Least-squares analyses were performed on a set of atomic masses using standard and generalized senaiempirical mass laws. Presumably because of errors in the assured form of the standand mass law, its least-squares coefficients can be determined at best to an accuracy of about 10%, and masses are predicted with an uncertainty of several Mev/c/sup 2/. The standard mass law was generalized by addition of shell effect and deformation terms. While the least-squares fitting of the generalized mass law is better than for the standard mass law, it is still not possible to predict atomic masses to an accuracy better than a few Mev/c/sup 2/. The nuclear deformations and the well depth . of the nuclear interaction obtained from the additional mass-law terms are in reasonable agreement with more accurate determinations by other methods. A similar statement applies to the nuclear ...
1959-11-15
Regulatory Framework for Advanced Fuel Cycle Facility Using Pyroprocess in Korea
International Nuclear Information System (INIS)
Nuclear power plants of 20 units of in Korea are generating about 700 MTU of spent fuels annually. The inventory of spent fuels in Korea were estimated about 10,087.07 MTU at end of 2008, and the storage space of spent fuels won't be available any more at 2016 due to the saturation of the spent fuel pools in the plants. In addition, in order to reduce carbon emission and correspond to the enormous electricity demand in Korea, 8 units of nuclear power plants are under construction and several more plants are under planning. The 100,000 MTU of spent fuel inventory are expected by the year of 2095 in Korea. Therefore, short term and long term of spent fuel management plans are under discussion and implementation in Korea. As a short term of spent fuel management strategy for the target year of 2016, central or local spent fuel dry interim storage options are mostly under discussion. As a long term of management plan, fast reactor and advanced fuel cycle R and D plan were approved by 255th ...
2010-10-01
Vulnerability Analysis of Physical Protection System at Wolsung Nuclear Power Plant
Energy Technology Data Exchange (ETDEWEB)
The 9/11 event in the U.S.A has increased international terror possibilities against nuclear facilities including nuclear power plants(NPPs). It is necessary to assess the performance of an existing physical protection system(PPS) at nuclear facilities based on such malevolent acts. A PPS is a complex configuration of detection, delay, and response elements. Several methods are available to analyze a PPS and evaluate its effectiveness. Sandia National Laboratory(SNL) in the USA was developed a System Analysis of Vulnerability to Intrusion (SAVI) computer code for this purpose. It is powerful software for evaluating the effectiveness of PPS against outsider threats. This study presents the performance assessment of the PPS at Wolsung NPP using SAVI code. First, the site-specific Adversary Sequence Diagrams(ASDs) of the PPS is constructed. It helps to understand the functions of the existing PPS composed ...
2006-07-01
Vulnerability Analysis of Physical Protection System at Wolsung Nuclear Power Plant
International Nuclear Information System (INIS)
The 9/11 event in the U.S.A has increased international terror possibilities against nuclear facilities including nuclear power plants(NPPs). It is necessary to assess the performance of an existing physical protection system(PPS) at nuclear facilities based on such malevolent acts. A PPS is a complex configuration of detection, delay, and response elements. Several methods are available to analyze a PPS and evaluate its effectiveness. Sandia National Laboratory(SNL) in the USA was developed a System Analysis of Vulnerability to Intrusion (SAVI) computer code for this purpose. It is powerful software for evaluating the effectiveness of PPS against outsider threats. This study presents the performance assessment of the PPS at Wolsung NPP using SAVI code. First, the site-specific Adversary Sequence Diagrams(ASDs) of the PPS is constructed. It helps to understand the functions of the existing PPS composed ...
2006-05-25
Photovoltaic industry manufacturing technology. Final report
Energy Technology Data Exchange (ETDEWEB)
This report contains the results of the Photovoltaic (PV) Industry Manufacturing Technology Assessment performed by the Automation and Robotics Research Institute (ARRI) of the University of Texas at Arlington for the National Renewable Energy laboratory. ARRI surveyed eleven companies to determine their state-of-manufacturing in the areas of engineering design, operations management, manufacturing technology, equipment maintenance, quality management, and plant conditions. Interviews with company personnel and plant tours at each of the facilities were conducted and the information compiled. The report is divided into two main segments. The first part of the report presents how the industry as a whole conforms to ``World Class`` manufacturing practices. Conclusions are drawn from the results of a survey as to the areas that the PV industry can improve on to become more competitive in the industry and World Class. Appendix A contains the ...
1998-08-01
International Nuclear Information System (INIS)
During the phases of separation, treatment, conditioning and storage of radioactive waste, destructive and nondestructive methods for their characterization are needed. In order to satisfy this necessity, in the frame of the National Program of Research and Development, the 'Laboratory for characterization of spent nuclear fuel and high/medium level radioactive waste- LABORAD' was created. The purpose of the project was to accredit the analysis methods available in the laboratory, and also to develop new methods for the characterization of the radioactive waste. A special attention was paid to the high-level radioactive waste and spent nuclear fuel characterization that require special facilities for handling. These facilities (e.g. hot cells, remote handlers, transport container) are already available in our institute. Experimental results and performances obtained during validation of the methods are presented in this ...
2009-05-27
COVFILS-2: neutron data and covariances for sensitivity and uncertainty analysis
Energy Technology Data Exchange (ETDEWEB)
The author have prepared a new, fusion-oriented library of multigroup neutron cross sections, scattering matrices, and covariances (uncertainties and correlations). The 74-group library, called COVFILS-2, has been used, or will be used, by neutronics groups at Los Alamos National Lab. (LANL) at the University of California at Los Angeles, and at the Swiss Federal Institute for Reactor Research in the sensitivity and uncertainty analysis of fusion-relevant integral experiments such as the Li/sub 2/O experiment performed at the Fast Neutron Source Facility in Japan and the Lithium breeding module experiment planned at the LOTUS facility in Lausanne, Switzerland. Another intended use of this library is in the estimation of the uncertainty in key performance parameters (such as the breeding ratio) of conceptual fusion reactors. The 14 materials included in the first version of COVFILS-2 are hydrogen, /sup ...
1986-01-01
COVFILS-2: neutron data and covariances for sensitivity and uncertainty analysis
International Nuclear Information System (INIS)
The author have prepared a new, fusion-oriented library of multigroup neutron cross sections, scattering matrices, and covariances (uncertainties and correlations). The 74-group library, called COVFILS-2, has been used, or will be used, by neutronics groups at Los Alamos National Lab. (LANL) at the University of California at Los Angeles, and at the Swiss Federal Institute for Reactor Research in the sensitivity and uncertainty analysis of fusion-relevant integral experiments such as the Li_2O experiment performed at the Fast Neutron Source Facility in Japan and the Lithium breeding module experiment planned at the LOTUS facility in Lausanne, Switzerland. Another intended use of this library is in the estimation of the uncertainty in key performance parameters (such as the breeding ratio) of conceptual fusion reactors. The 14 materials included in the first version of COVFILS-2 are hydrogen, "6Li, "7Li, ...
1986-06-15
Energy Technology Data Exchange (ETDEWEB)
This report presents the results of Run 260 performed at the Advanced Coal Liquefaction R&D Facility in Wilsonville. The run was started on July 17, 1990 and continued until November 14, 1990, operating in the Close-Coupled Integrated Two-Stage Liquefaction mode processing Black Thunder mine subbituminous coal (Wyodak-Anderson seam from Wyoming Powder River Basin). Both thermal/catalytic and catalytic/thermal tests were performed to determine the methods for reducing solids buildup in a subbituminous coal operation, and to improve product yields. A new, smaller interstage separator was tested to reduce solids buildup by increasing the slurry space velocity in the separator. In order to obtain improved coal and resid conversions (compared to Run 258) full-volume thermal reactor and 3/4-volume catalytic reactor were used. Shell 324 catalyst, 1/16 in. cylindrical extrudate, at a replacement rate of 3 lb/ton of MF coal was ...
1992-01-01
Advanced Coal Liquefaction Research and Development Facility, Wilsonville, Alabama
Energy Technology Data Exchange (ETDEWEB)
This report presents the results of Run 260 performed at the Advanced Coal Liquefaction R D Facility in Wilsonville. The run was started on July 17, 1990 and continued until November 14, 1990, operating in the Close-Coupled Integrated Two-Stage Liquefaction mode processing Black Thunder mine subbituminous coal (Wyodak-Anderson seam from Wyoming Powder River Basin). Both thermal/catalytic and catalytic/thermal tests were performed to determine the methods for reducing solids buildup in a subbituminous coal operation, and to improve product yields. A new, smaller interstage separator was tested to reduce solids buildup by increasing the slurry space velocity in the separator. In order to obtain improved coal and resid conversions (compared to Run 258) full-volume thermal reactor and 3/4-volume catalytic reactor were used. Shell 324 catalyst, 1/16 in. cylindrical extrudate, at a replacement rate of 3 lb/ton of MF coal was used ...
1992-01-01
Energy Technology Data Exchange (ETDEWEB)
Some diagnostics at the National Ignition Facility (NIF), including the Gamma Reaction History (GRH) diagnostic, require multiple channels of data to achieve the required dynamic range. These channels need to be stitched together into a single time series, and they may have non-uniform and redundant time samples. We chose to apply the popular cubic smoothing spline technique to our stitching problem because we needed a general non-parametric method. We adapted one of the algorithms in the literature, by Hutchinson and deHoog, to our needs. The modified algorithm and the resulting code perform a cubic smoothing spline fit to multiple data channels with redundant time samples and missing data points. The data channels can have different, time-varying, zero-mean white noise characteristics. The method we employ automatically determines an optimal smoothing level by minimizing the Generalized Cross Validation (GCV) score. In order to automatically ...
2010-12-28
An Introduction to the Standard Theory of Electroweak Interactions (4/4)
An Introduction to the Standard Theory of Electroweak Interactions (4/4)
2011-01-01
An Introduction to the Standard Theory of Electroweak Interactions (3/4)
An Introduction to the Standard Theory of Electroweak Interactions (3/4)
2011-01-01
An Introduction to the Standard Theory of Electroweak Interactions (2/4)
An Introduction to the Standard Theory of Electroweak Interactions (2/4)
2011-01-01
Energy Technology Data Exchange (ETDEWEB)
An overall view of the 1982 plant operating performance is presented. All periods of ON-FEED operation, UNSCHEDULED SHUTDOWNS, and SCHEDULED SHUTDOWNS are accounted for and tabulated. Causes of UNSCHEDULED SHUTDOWNS are identified and discussed. Plant solutions aimed at reducing the effect of similar future shutdowns or preventing recurrence of such shutdowns are explained. Details of repeated, major maintenance problems with various pieces of equipment are presented. Discussion of each problem and solutions found during 1982 are given, where applicable.
1983-12-01
Energy Technology Data Exchange (ETDEWEB)
This study investigates spent fuel cask handling experience at existing nuclear facilities to determine appropriate cask decontamination and maintenance operations at the potential Yucca Mountain repository. These operations are categorized as either routine or nonroutine. Routine cask decontamination and maintenance tasks are performed in the cask preparation area at the repository. Casks are taken offline to a separate cask maintenance area for major nonroutine tasks. The study develops conceptual designs of the cask preparation area and cask maintenance area. The functions, layouts, and major features of these areas are also described.
1992-04-01
International Nuclear Information System (INIS)
Thermal analysis testing revealed slight weight changes, which were a function of gamma irradiation, in a highly reduced Defense Waste Processing Facility (DWPF) simulated waste glass. Transmission electron microscopy (TEM) was performed on this glass to determine if the weight change corresponded to microstructural variations. TEM analyses showed that no microstructural changes were attributable to gamma irradiation. Exposure of the samples to the electron beam in the TEM did cause changes in the glass microstructures in some cases. These changes were likely due to localized heating of the glass due to interactions with the transmitted electrons.
1994-04-25
The use of combustible metals in explosive incendiary devices
Energy Technology Data Exchange (ETDEWEB)
We have investigated tailoring damage effects of explosive devices by addition of unconventional materials, specifically combustible metals. Initial small-scale as well as full-scale testing has been performed. The explosives functioned to disperse and ignite these materials. Incendiary, enhanced-blast, and fragment-damage effect have been identified. These types of effects can be used to extend the damage done to hardened facilities. In other cases it is desirable to disable the target with minimal collateral damage. Use of unconventional materials allows the capability to tailor the damage and effects of explosive devices for these and other applications. Current work includes testing of an incendiary warhead for a penetrator.
1996-08-01
State of Surgery in Tropical Africa: A Review
British Library Electronic Table of Contents (United Kingdom)
This is a review of recently published literature on surgery in tropical Africa. It presents the current state of surgical need and surgical practice on the continent. We discuss the enormous burden of surgical pathology (as far as it is known) and the access to and acceptability of surgery. We also describe the available facilities in terms of equipment and manpower. The study looked at the effects of the human immunodeficiency virus, the role of traditional healers, anesthesia, and the economics of surgery. Medical training and research are discussed, as are medical migration out of Africa and the concept of task shifting, where surgical procedures are performed by others when surgeons are not available. It closes with recommendations for involvement and action in this area of great glob...
2011-01-01
Simultaneous measurement of the neutron capture and fission yields of "2"3"3U
International Nuclear Information System (INIS)
We have measured the neutron capture and fission cross section of "2"3"3U at the neutron time-of-flight facility n-TOF at CERN in the energy range from 1 eV to 1 MeV with high accuracy by using a high performance 4#pi# BaF_2 Total Absorption Calorimeter (TAC) as a detection device. The method, based on the shape analysis of the TAC energy response, allowing to disentangle between #gamma#'s originating from fission and capture will be presented as well as the first very preliminary results. (authors)
2007-04-22
Energy Technology Data Exchange (ETDEWEB)
The performance of a high temperature ion source coupled to a helium gas-jet transport system for an efficient mass separation of neutron-rich alkaline earth and lanthanide isotopes is reported and the results of overall efficiency measurements using different cluster materials in the gas-jet are given. A fast, microprocessor controlled tape transport system for ..gamma..-spectroscopic studies on short-lived isotopes is described. Some results on the decay of 3.8sub(-s) /sup 152/Pr are presented. (orig.).
1985-02-01
Energy Technology Data Exchange (ETDEWEB)
The performance of a high temperature ion source coupled to a helium gas-jet transport system for an efficient mass separation of neutron-rich alkaline earth and lanthanide isotopes is reported and the results of overall efficiency measurements using different cluster materials in the gas-jet are given. A fast, microprocessor controlled tape transport system for ..gamma..-spectroscopic studies on short-lived isotopes is described. Some results on the decay of 3.8sub(-s) /sup 152/Pr are presented.
1985-02-01
In situ observation of axial irradiation growth in liquid-metal reactor metal fuel
International Nuclear Information System (INIS)
Effects of the rapid early-in-life expansion of metal fuel were measured in an irradiation experiment in the Fast Flux Test Facility (FFTF). This important performance/design information was obtainable through the unique combination of a dimensionally stable FFTF oxide core and the calibrated proximity instrumentation associated with the test. These results delineate the time dependence of metal-fuel swelling and provide quantitative estimates of the magnitude of axial fuel swelling in full-length metal-fuel assemblies. Final posttest examination results will define actual fuel column growth levels.
1989-11-26
Distributed-processing radiation management system for nuclear power plants
Energy Technology Data Exchange (ETDEWEB)
The importance of radiation management for nuclear facilities including nuclear power plants has increased as the general public understanding has progressed, and necessary information for management must be processed exactly and quickly. In nuclear power plants, radiation management is performed by each individual operation, and collected information is managed by the system of each operation. The distributed-processing radiation management system has been developed aiming to use a general-purpose LAN and make quick and efficient use of information managed by individual operations. This paper describes the system configuration and functions. (author)
1999-06-01
International Nuclear Information System (INIS)
A comparative assessment of five different heat transfer configurations for operation in compact heat exchangers is presented. The configurations under consideration are four standaed heat exchanger surfaces - two plain fin, an offset strip and a louvered fin geometry - and one surface with so called vortex generators for heat transfer augmentation. In the case of the standard surfaces, the basic performance characteristics in the form of heat transfer and friction data versus the Reynolds number have been taken from published experimental results. In the case of the vortex generator surface, the performance characteristics have been derived from a numerical prediction of the flow and temperature field in a closely spaced parallel plate channel with vortex generators in the form of delta wings mounted on the channel walls. In comparison to the plain fin surfaces with a rectangular cross section, the vortex generator surface ...
1993-01-01
Energy Technology Data Exchange (ETDEWEB)
The study presented in this thesis is a contribution toward improving the reliability of Metallized Polypropylene Film (MPPF) capacitors achieved by a better design. A temperature distribution in the roll is assumed with the aim of optimizing its thermal performance. It appears that the heating of long capacitor is higher than that of equivalent flat capacitor subjected to the same electric stresses. Standard accelerated aging tests (temperature and voltage) of MPPF capacitors have been performed with the aim to evaluate the dielectric performance and thus the capacitor lifetime. The statistical approach showed that the failure mode may be represented by two parameter Weibull distribution and the experimental approach proved that long capacitor deteriorates faster than a plate-shaped having the same features. Although capacitors with long geometry seem to have a poor pulse handling ...
2001-12-01
Energy Technology Data Exchange (ETDEWEB)
ATLAS is one of the four experiments which will take place at the LHC, the CERN future protons collider. This accelerator, which should start in 2007, will allow to continue the studies carried out by its predecessors, as the standard model Higgs boson and new physics searches. The very high luminosity -10 fb{sup -1} during the first three functioning years, then 100 fb{sup -1}- and the 14 TeV in the frame center will ease these studies. The Centre de Physique des Particules de Marseille took part in the ATLAS collaboration, taking in charge half of the End-cap electromagnetic calorimeter modules construction. The description of this sub-detector and the construction steps, in particular the electrical tests which allow the stacking validation, are presented in this document. These tests results, obtained for the live first production modules, are analysed. The pre-series module (module 0) performances, obtained with beam tests ...
2002-09-01
International Nuclear Information System (INIS)
This plan establishes both the scope of the review and the acceptance criteria to be utilized for the review of Quality Assurance Program Plans (QAPPs) developed in accordance with the requirements of DOE/RL-90-28. DOE/RL-90-28, the Environmental Restoration Remedial Action Quality Assurance Requirements Document (QARD) defines all quality assurance (QA) requirements governing activities that affect the quality of the Environmental Restoration Remedial Action (ERRA) program at the Hanford Site. These requirements are defined in three parts, Part 1 of Quality Management and Administration tasks, Part 2 for Environmental Data Operations, and Part 3 of the Design and Construction of items, systems, and facilities. The purpose of this document is to identify the scope of the review by the DOE Field Office, Richland staff, and establish the acceptance criteria (Parts 1, 2, and 3) that the DOE Field Office, Richland staff will utilize to evaluate the participant QAPPs. ...
F-Area Seepage Basins groundwater monitoring report -- third and fourth quarters 1993. Volume 1
Energy Technology Data Exchange (ETDEWEB)
During the second half of 1993, the groundwater at the F-Area Seepage Basins (FASB) was monitored in compliance with Module 3, Section C, of South Carolina Hazardous Waste Permit SC1-890-008-989, effective November 2, 1992. The monitoring well network is composed of 87 FSB wells screened in the three hydrostratigraphic units that make up the uppermost aquifer beneath the FASB. A detailed description of the uppermost aquifer is included in the Resource Conservation and Recovery Act Part B post-closure care permit application for the F-Area Hazardous Waste Management Facility submitted to the South Carolina Department of Health and Environmental Control (SCDHEC) in December 1990. Beginning in the first quarter of 1993, the standard for comparison became the SCDHEC Groundwater Protection Standard (GWPS) specified in the approved F-Area Seepage Basins Part B permit. Currently and historically, gross alpha, nitrate, nonvolatile ...
1994-03-01
Analysis of Elements in The Baltic Sea Sediment by Using Gamma Spectrometry
International Nuclear Information System (INIS)
We have done analysis of elements in the Baltic sea sediment by using gamma spectrometry in neutron activation analysis Goal of the analysis is to determine the rate of morsel elements which is contained in the Baltic sea sediment. Sample of the Baltic sea Sediment (IAEA-SED-1), Standard of Reference Material (SRM) 1646 Estuarine Sediment and Standard Ce, Fe, Sc, and Co are put into vial of capsule rabbit, then irradiated together for 30 minutes in rabbit facility Multi Purpose Reactor at power of 25 MW and then cooled for one week. Next sample, standard, and SRM which have irradiated, each is cut for 30 minutes using gamma spectrometer. Result of analysis of rate of elements Ce, Fe, Sc and Co in the baltic sea sediment successively equal to 141.20 ppm, 5.91 %, 14.88 ppm, and 19.59 ppm. Result of analysis in SRM Estuarine sediment successively equal to 96.60 ppm, 3.21 %, 10.25 ppm, and 9.63 ppm. Result ...
2007-04-01
A quality approach to maintain the properties of S235 JR structural carbon steel in Lebanon
International Nuclear Information System (INIS)
Full text.S235JR carbon steel is one of the most popular steels used in Lebanon. It is imported by steel dealers and is widely used by all fabricators and manufacturers of steels for many structural purposes and applications. This kind of steel has good ductile properties as well as excellent weldability. It is still known by its previous designation St 37-2 or E 24-2. S235JR is produced in many shapes and thicknesses such as steel plates, sheets, angles and different other geometric shapes. Standard chemical and mechanical tests were conducted and reported on S235JR hot-rolled structural low-carbon mild steel specimens collected from Lebanese steel market. The main objective of this work is to assure the compliance of these properties with those set by the steel manufacturer. The above mentioned tests were performed at the laboratories of the Industrial Research Institute (IR) in Lebanon to assure the quality and credibility of the results. ...
2004-05-26
Energy Technology Data Exchange (ETDEWEB)
The {sup 252}Cf-source-driven noise analysis method has been used in measurements for subcritical configurations of fissile systems for a variety of applications. Measurements of 25 fissile systems have been performed with a wide variety of materials and configurations. This method has been applied to measurements for (1) initial fuel loading of reactors, (2) quality assurance of reactor fuel elements, (3) fuel preparation facilities, (4) fuel processing facilities, (5) fuel storage facilities, (6) zero-power testing of reactors, and (7) verification of calculational methods for assemblies with the neutron k < l. These previous measurements, performed with a wide variety of multiplying systems, demonstrated the usefulness of the method. The high sensitivity of noise-measured parameters to small changes in fissile systems has been observed in several measurements. This high ...
1993-10-01
Performance assessment for the disposal of low-level waste in the 200 east area burial grounds
Energy Technology Data Exchange (ETDEWEB)
A performance assessment analysis was completed for the 200 East Area Low-Level Burial Grounds (LLBG) to satisfy compliance requirements in DOE Order 5820.2A. In the analysis, scenarios of radionuclide release from the 200 East Area Low-Level waste facility was evaluated. The analysis focused on two primary scenarios leading to exposure. The first was inadvertent intrusion. In this scenario, it was assumed that institutional control of the site and knowledge of the disposal facility has been lost. Waste is subsequently exhumed and dose from exposure is received. The second scenario was groundwater contamination.In this scenario, radionuclides are leached from the waste by infiltrating precipitation and transported through the soil column to the underlying unconfined aquifer. The contaminated water is pumped from a well 100 m downstream and consumed,causing dose. Estimates of potential contamination of the surrounding ...
1996-08-15
Boil-off experiments with the EIR-NEPTUN Facility: Analysis and code assessment overview report
International Nuclear Information System (INIS)
The NEPTUN data discussed in this report are from core uncovery (boil-off) experiments designed to investigate the mixture level decrease and the heat up of the fuel rod simulators above the mixture level for conditions simulating core boil-off for a nuclear reactor under small break loss-of-coolant accident conditions. The first series of experiments performed in the NEPTUN test facility consisted of ten boil-off (uncovery) and one adiabatic heat-up tests. In these tests three parameters were varied: rod power, system pressure and initial coolant subcooling. The NEPTUN experiments showed that the external surface thermocouples do not cause a significant cooling influence in the rods to which they are attached under boil-off conditions. The reflooding tests performed later on indicated that the external surface thermocouples have some effect during reflooding for NEPTUN electrically heated rod bundle. Peak cladding ...
Space reactor fuel element testing in upgraded TREAT
Energy Technology Data Exchange (ETDEWEB)
The testing of candidate fuel elements at prototypic operating conditions with respect to temperature, power density, hydrogen coolant flow rate, etc., a crucial component in the development and qualification of nuclear rocket engines based on the Particle Bed Reactor (PBR), NERVA-derivative, and other concepts. Such testing may be performed at existing reactors, or at new facilities. A scoping study has been performed to assess the feasibility of testing PBR based fuel elements at the TREAT reactor. initial results suggest that full-scale PBR, elements could be tested at an average energy deposition of {approximately}60--80 MW-s/L in the current TREAT reactor. If the TREAT reactor was upgraded to include fuel elements with a higher temperature limit, average energy deposition of {approximately}100 MW/L may be achievable.
1993-05-01
Food and biomass production in small oil expression facilities
Energy Technology Data Exchange (ETDEWEB)
This paper reported on a study in which rapeseeds were separated into high quality seed for food oil and low quality seed for biofuels. A laboratory-scale oilseed screw press was then used to examine the effects of choke opening and seed preheating on the rapeseed pressing performance and the quality of food oil and biofuels oil. Oil recovery and chlorophyll content was found to increase as maximum pressure increased. In terms of pressing performance, the rapeseed heated by microwaves yielded more oil and chlorophyll than without heating. The NEB ratio of microwave heating press with an 8.0 mm choke opening was advantageous. Rapeseed oil extracted from low quality seeds was found to have a high acid value. The quality of oil extracted by oilseed screw press was found to be good and met the requirements of the Codex Alimentarius for edible oils.
2010-07-01
Fingerprint testing of contaminated ventilation extract filter systems at Sizewell B
International Nuclear Information System (INIS)
Sizewell B is Nuclear Electric's latest power station, and the Pressurised Water Reactor (PWR) design on which it is based represents a ''first'' for the UK. One of the integral components of the plant is the heating, ventilation and air-conditioning (HVAC) system, which performs a contamination control and gaseous waste management function for the site. During the commissioning of Sizewell B Power Station the extract systems of the HVAC plant underwent a procedure known as ''fingerprinting''. This entailed the characterisation of the facilities provided to test the filtration plant during its lifetime. The assessment of their adequacy was then used to identify necessary modifications and/or to propose the manner in which future in situ performance testing would be carried out. The paper outlines the basic principles and procedure that was used to ''fingerprint'' test systems during the commissioning of Sizewell B. A ...
Energy savings opportunity survey. US Army Field Station Kunia, Oahu, Hawaii. Final report
This Energy Savings Opportunity Survey (ESOS) is to identify Energy Conservation Opportunities (ECO`s) which are practical and economical for the reduction of energy consumption in accordance with the Army Facilities Energy Plan. The work to be performed under this project includes: (A) Coordinating with the on-going and proposed related projects. (B) Conducting a limited site survey required to identify applicable ECO`s and obtaining necessary data to evaluate the ECO`s. (C) Evaluating applicable ECO`s to determine their feasibility in accordance with current criteria. (D) Preparing programming and implementation documents for the recommended ECO`s. and (E) Preparing a comprehensive report to present the work performed including energy analysis, the results, and recommendations.
1989-06-01
Core demonstration lead experiments for irradiation in FFTF
International Nuclear Information System (INIS)
A major new initiative to develop and irradiate a long-life mixed oxide fuel system in the Fast Flux Test Facility (FFTF) has been implemented by the Westinghouse Hanford Company at the Hanford Engineering Development Lab. for the US Dept. of Energy. The purpose of this new fuel system, called the Core Demonstration Experiment (CDE), is to demonstrate the capability of achieving a 3-yr life in a prototypical heterogeneous reactor environment under prototypical power and temperature conditions. Three Core Demonstration Lead Experiments (CDLEs) will establish the performance characteristics of entire fuel assemblies of wire-wrapped, large diameter, advanced oxide fuel pins with HT-9 stainless steel alloy cladding and wire wrap and an HT-9 duct. Their performance characteristics provided the basis for design, fabrication, and irradiation of the CDE.
1987-06-07
An intelligent design methodology for nuclear power systems
Energy Technology Data Exchange (ETDEWEB)
The goal of this investigation is to research possible methodologies into automating the design of, specifically, nuclear power facilities; however, it is relevant to all thermal power systems. The strategy of this research has been to concentrate on individual areas of the thermal design process, investigate procedures performed, develop methodology to emulate that behavior, and prototype it in the form of a computer program. The design process has been generalized as follows: problem definition, design definition, component selection procedure, optimization and engineering analysis, testing and final design with the problem definition defining constraints that will be applied to the selection procedure as well as design definition. The result of this research is a prototype computer program applying an original procedure for the selection of the best set of real components that would be used in constructing a system with desired ...
1989-01-01
A study on the transient piping vibration of power plant. Secondary piping system of Wolsung 1 unit
Energy Technology Data Exchange (ETDEWEB)
In order to maintain a safe operation and availability of generating facilities, qualitative and quantitative assessment of piping vibration was performed vibration sources and damages of piping support was identified on the second piping system of Wolsung nuclear power plant unit 1 .Inspected piping supports and structures in both hot and cold condition .Established evaluation procedures of piping vibration .Performed the static analysis of 2 nd piping system .Established optimal vibration reducing method .The measured vibration level after installing rigid supports and energy absorbing type restraint was reduced about 7 times in velocity unit (author). 24 refs., 95 figs.
1996-08-01
LOBI/B-R1M, Loop for Blowdown Investigation, PWR Single-Ended Cold-Leg Break Experiment B EXP.B
International Nuclear Information System (INIS)
1 - Description of test facility: The LOBI facility is a 1/700 scale model of a four loop PWR and has two primary loops, the intact loop representing three loops and the broken loop representing one loop of a four-loop PWR. The reactor pressure vessel model contains an electrically heated rod-bundle with 64 rods and a heated length of 3.9 m. The nominal heating power is 5.3 MW. The downcomer is of annular shape. An upper head simulator is connected to the vessel. Each of the two primary loops contains a pump and a steam generator. The different mass flows in the loops are established by the pump speeds, since the two pumps are identical. Heat is removed from the steam generators by a secondary system. ECC water can be supplied from two accumulators, one for each loop. Cold or hot leg as well as combined injection can be simulated. The LOBI test facility is the only high pressure integral test facility ...
Energy Technology Data Exchange (ETDEWEB)
With an objective to use reproducible vegetable oil as a substitute fuel, studies were performed to use emulsified rapeseed oil at an optimal mixing ratio with water in a direct injection diesel engine. The experiment used a water cooled, lateral installation, single-cylinder, direct injection, four-cycle diesel engine, and the tested fuel used an emulsified rapeseed oil fuel with rapeseed oil added with water at a rate of 20% by weight. As a result of the experiment using the emulsified rapeseed oil, it was found that reducing the injection opening diameter smaller than the standard opening diameter improves the engine performance and simultaneously reduces concentrations of HC, CO and exhaust smoke. The optimal opening diameter was about 0.22 mm. Increasing the valve opening pressure reduced the NOx concentration, but increased the HC concentration. Using the emulsified rapeseed oil fuel accumulated more carbon below the ...
1994-09-30
Testing of Critical Features of Polysilicon MEMS
Energy Technology Data Exchange (ETDEWEB)
The behavior of MEMS devices is limited by the strength of critical features such as thin ligaments, oxide cuts joining layers, pin joints and hinges. Devices fabricated at Sandia's Microelectronic Development Laboratory have been successfully tested to investigate these features. A series of measurements were performed on samples with gage lengths of 15 to 1000 microns, using conventional and tungsten coated samples as well as samples that include the critical features of standard components in the test section. Specimens have a freely moving pin joint on one end that anchors the sample to the silicon die to allow rotation to reduce effects of bending. Each sample is loaded in uniaxial tension by pulling laterally with a flat tipped diamond in a computer-controlled Nanoindenter. Load is calculated by resolving the measured lateral and normal forces into the applied tensile force and frictional losses. The specimen cross section and ...
1999-12-02
Energy Technology Data Exchange (ETDEWEB)
The Department prepared the Fiscal Year 1998 Accountability Report to combine critical financial and program performance information in a single report. The Department`s consolidated financial statements and the related audit reports are included as major components of the Accountability Report. The Office of Inspector General audited the Department`s consolidated financial statements as of and for the years ended September 30, 1998 and 1997. In the opinion of the Office of Inspector General, except for the environmental liabilities lines items in Fiscal year 1998, these financial statements present fairly, in all material respects, the financial position of the Department as of September 30, 1998 and 1997, and its consolidated net cost, changes in net position, budgetary resources, financing activities, and custodial activities for the years then ended in conformity with Federal accounting standards. In accordance with Government Auditing ...
1999-02-01
Energy Technology Data Exchange (ETDEWEB)
Trichlorfon is an organophosphorus insecticide, which is extensively being used for protection of fruit crops. Trichlorfon is a thermal labile compound, which cannot be easily determined by gas chromatography (GC) and has no suitable group for sensitive detection by high performance liquid chromatography (HPLC). In this study, a {sup 31}P nuclear magnetic resonance ({sup 31}P NMR) has been described for monitoring of trichlorfon without any separation step. The quantitative works of {sup 31}P NMR spectroscopy has been performed in the presence of an internal standard (hexamethylphosphoramide). Limit of detection (LOD) for this method has been found to be 55 mg L{sup -1}, without any sample preparation, and the linear working range was 150-5500 mg L{sup -1}. Relative standard deviation (R.S.D.%) of the method for three replicates within and between days was obtained {<=}9%. The average recovery ...
2006-08-25
H{infinity} Control Synthesis for Power System Stabilizer Design using LMI Optimization Method
Energy Technology Data Exchange (ETDEWEB)
This paper presents the application of H{infinity} control synthesis using LMI optimization method to power system stabilizer(PSS) design. Since power system is usually operated under circumstance of unmeasurable uncertainties and external disturbances, the improvement of small signal stability becomes one of the most important issue for securing system stability and preventing low frequency oscillation phenomena. The LMI optimized H{infinity} PSS provides robust performance and guarantees the internal stability under these operating conditions. The global optimal H{infinity} norm is found using LMI convex optimization method which is more systematic than standard two Riccati solution method. The design results are simulated for a case study. We verified that the LMI method shown the best performance characteristic among standard Riccati method and conventional lead/lag method. (author). 19 refs., 12 ...
2000-04-01
Ageing assessments with application of PSA Models
International Nuclear Information System (INIS)
One of the main applications of PSA studies is related to identification of the major key issues related to plant safety. In standard PSA one assumes a constant value for component failure rates by considering that the component doesn't experience any degradation that could affect its performance. Used in this manner, standard PSA tools do not adequately address important ageing issues, and this fact could have a significant impact on the conclusions drawn from PSA studies and applications, in conditions of operation of ageing plants. To obtain realistic results, it is necessary to consider in the PSA model the ageing effects, and to do that it is necessary to take into consideration the change in component failure rate as a function of component age. In case of ageing phenomena, this dependence causes the failure rate of a component (or a set of components) to increase in time as the component age increase. The paper ...
2009-10-12
Energy Technology Data Exchange (ETDEWEB)
Preliminary results of studies into penetrant testing at high surface temperature (up to 200 deg.C), are presented. Tests were performed to assess the effectiveness of red dye penetrants using Al and NiCr samples containing artificial as well as natural discontinuities. The test results will be used in due course to formulate a specification for non-destructive testing procedure qualification at non-standard (i.e. outside 16-52 deg.C) temperatures.
2000-04-01
Energy Technology Data Exchange (ETDEWEB)
Procedures followed in designing for offshore production rigs in the Northeastern Areas of the Campos Basin are presented. Various advantages afforded by the mast in the performance of required tasks are analyzed, along with all calculation premises and methods for adequate sizing. Standards covering mast design, materials used in manufacture, and test routines are also examined. (author). 16 figs., 3 tabs., 11 refs
1989-07-01
Making resource recovery economical
Energy Technology Data Exchange (ETDEWEB)
Four major reasons why municipal resource recovery operations are uneconomical are analyzed. These reasons are: alternative municipal waste disposal methods are artificially underpriced when the costs of meeting modern environmental standards are considered; high capital costs related to the procurement of resource recovery systems and the marketing of recovered resources; uncertainties associated with the costs and performance of resource recovery technologies; and construction and operating risks of municipal waste resource recovery systems. If resource recovery is to become economical, purchasers of plants must develop innovative process designs and equipment and formulate new operating and maintenance procedures. (1 photo)
1980-01-01
Energy Technology Data Exchange (ETDEWEB)
The authors have developed a complex of activation methods of analysis using a nuclear reactor (nuclear activation analysis) and a cyclotron (charged-particle activation analysis). The methods have been used to determine the concentrations of more than 20 elements in five medicinal plants native to Uzbekistan: Syrian rue (Peganum harmala L.), plantain (Plantago lanceolata), peppermint (Mentha piperata L.), sage (Salvia officinalis L.), and ziziphora (Ziziphora bungeana Yur.). The results of radio-activation analysis were compared with the results of standard spectral analysis performed in another laboratory and the accuracy of the procedures developed was evaluated on the basis of the results.
1987-06-01
Energy Technology Data Exchange (ETDEWEB)
The purpose of the chapter is to explain briefly the various considerations that enter into determining the general layout or arrangement of typical hydroelectric powerplants, pumping plants, and pumped-storage plants. Some of the important factors that affect or determine the location, type, and layout of the plant and the selection of the major items of equipment included in the installation are outlined in this chapter. The first consideration in the design of a powerplant, pumping plant, or pumped-storage plant is that it adequately perform its function and be structurally safe. The structure is also designed to give a pleasing architectural appearance.
1985-05-01
Convective heat transfer under unsteady impinging jets: the effect of the shape of the unsteadiness
Unsteady impinging jets are systematically controlled with respect to their time dependence in order to investigate the influence of unsteadiness on the heat transfer performance. This is achieved by a special mass flow control device, which allows almost arbitrary shapes of unsteadiness to be imposed onto the impinging jet. Three different standard signals (sinusoidal, triangular, rectangular) and two specially designed signals are applied and their influence on heat transfer is determined in terms of an enhancement factor. Heat transfer augmentation up to 30% was found and could be physically explained with the help of PIV and hot-wire measurements of the flow field.
2009-10-01
Energy Technology Data Exchange (ETDEWEB)
This conference is composed of 21 communications and 21 posters in the domain of building ventilation and indoor air quality; the main themes are: indoor air quality assessment and optimization; performance enhancement and optimization of ventilation systems and equipment; ventilation systems for renovated and rehabilitated buildings; French and European regulations, standardizations and certifications; experimental and numerical simulation studies concerning ventilation systems, air flow, temperature distribution, air quality, thermal comfort and ventilation-induced acoustic levels
1995-10-01
Energy Technology Data Exchange (ETDEWEB)
Safe and economical operations with fissile materials require knowledge of the subcriticality of configurations that arise in material processing, storage, and transportation. Data from critical experiments have been a principal source of information with which to establish safety margins. However, the lower cost and the expediency of performing confirmatory subcritical measurements on the process floor or in the storage vault resulted in much of the early criticality safety guidance being based on subcritical in situ experiments.
1996-10-01
A review of best practices for Monte Carlo criticality calculations
Energy Technology Data Exchange (ETDEWEB)
Monte Carlo methods have been used to compute k{sub eff} and the fundamental mode eigenfunction of critical systems since the 1950s. While such calculations have become routine using standard codes such as MCNP and SCALE/KENO, there still remain 3 concerns that must be addressed to perform calculations correctly: convergence of k{sub eff} and the fission distribution, bias in k{sub eff} and tally results, and bias in statistics on tally results. This paper provides a review of the fundamental problems inherent in Monte Carlo criticality calculations. To provide guidance to practitioners, suggested best practices for avoiding these problems are discussed and illustrated by examples.
2009-01-01
A practical scheme for error control using feedback
We describe a scheme for quantum error correction that employs feedback and weak measurement rather than the standard tools of projective measurement and fast controlled unitary gates. The advantage of this scheme over previous protocols (for example Ahn et. al, PRA, 65, 042301 (2001)), is that it requires little side processing while remaining robust to measurement inefficiency, and is therefore considerably more practical. We evaluate the performance of our scheme by simulating the correction of bit-flips. We also consider implementation in a solid-state quantum computation architecture and estimate the maximal error rate which could be corrected with current technology.
2004-01-01
Synthesis and electrochemical performance of carbon nanofiber-cobalt oxide composites
Energy Technology Data Exchange (ETDEWEB)
Carbon nanofiber (CNF) supported cobalt oxide composites as high-capacity anode materials were prepared through a facile, effective method for potential use in rechargeable lithium-ion batteries. The effects of the calcining temperature on the crystallinity, grain size, specific surface area of Co{sub 3}O{sub 4} and phase transformation from Co{sub 3}O{sub 4} to CoO were studied in detail. Both the specific surface area and CNF content in CNF-cobalt oxide composites strongly affect the electrochemical performance of these series composites. The CNF-Co{sub 3}O{sub 4} composite with 24.3% CNF pyrolyzed at 500 deg. C in Ar shows an excellent cycling performance, retaining a specific capacity of 881 mAh g{sup -1} beyond 100 cycles. Homogeneous deposition and distribution of nanosized Co{sub 3}O{sub 4} particles on the surface of CNF can stabilize the electronic and ionic conductivity as well as the morphology of Co{sub 3}O{sub ...
2008-10-15
Synthesis and electrochemical performance of carbon nanofiber-cobalt oxide composites
Energy Technology Data Exchange (ETDEWEB)
Carbon nanofiber (CNF) supported cobalt oxide composites as high-capacity anode materials were prepared through a facile, effective method for potential use in rechargeable lithium-ion batteries. The effects of the calcining temperature on the crystallinity, grain size, specific surface area of Co{sub 3}O{sub 4} and phase transformation from Co{sub 3}O{sub 4} to CoO were studied in detail. Both the specific surface area and CNF content in CNF-cobalt oxide composites strongly affect the electrochemical performance of these series composites. The CNF-Co{sub 3}O{sub 4} composite with 24.3% CNF pyrolyzed at 500{sup o}C in Ar shows an excellent cycling performance, retaining a specific capacity of 881 mAh g{sup -1} beyond 100 cycles. Homogeneous deposition and distribution of nanosized Co{sub 3}O{sub 4} particles on the surface of CNF can stabilize the electronic and ionic conductivity as well as the morphology of Co{sub 3}O{sub ...
2008-10-15
Posttest analysis of the FFTF inherent safety tests
Energy Technology Data Exchange (ETDEWEB)
Inherent safety tests were performed during 1986 in the 400-MW (thermal) Fast Flux Test Facility (FFTF) reactor to demonstrate the effectiveness of an inherent shutdown device called the gas expansion module (GEM). The GEM device provided a strong negative reactivity feedback during loss-of-flow conditions by increasing the neutron leakage as a result of an expanding gas bubble. The best-estimate pretest calculations for these tests were performed using the IANUS plant analysis code (Westinghouse Electric Corporation proprietary code) and the MELT/SIEX3 core analysis code. These two codes were also used to perform the required operational safety analyses for the FFTF reactor and plant. Although it was intended to also use the SASSYS systems (core and plant) analysis code, the calibration of the SASSYS code for FFTF core and plant analysis was not completed in time to perform pretest ...
1987-01-01
Posttest analysis of the FFTF inherent safety tests
International Nuclear Information System (INIS)
Inherent safety tests were performed during 1986 in the 400-MW (thermal) Fast Flux Test Facility (FFTF) reactor to demonstrate the effectiveness of an inherent shutdown device called the gas expansion module (GEM). The GEM device provided a strong negative reactivity feedback during loss-of-flow conditions by increasing the neutron leakage as a result of an expanding gas bubble. The best-estimate pretest calculations for these tests were performed using the IANUS plant analysis code (Westinghouse Electric Corporation proprietary code) and the MELT/SIEX3 core analysis code. These two codes were also used to perform the required operational safety analyses for the FFTF reactor and plant. Although it was intended to also use the SASSYS systems (core and plant) analysis code, the calibration of the SASSYS code for FFTF core and plant analysis was not completed in time to perform pretest ...
1987-06-07
Determination of Shear Properties in the Upper Seafloor Using Seismo-acoustic Interface Waves
Energy Technology Data Exchange (ETDEWEB)
This thesis develops methods for recording and analysis of seismo-acoustic interface waves for determination of shear wave velocity as a function of depth and includes this in standard refraction seismic surveying. It investigates different techniques for estimation of dispersion characteristics of the interface waves and demonstrates that multi sensor spectral estimation techniques improve the dispersion estimates. The dispersion estimate of the fundamental interface wave mode is used as input to an object function for a model based linearized inversion. The inversion scheme provides an estimate of the shear wave velocity as a function of depth. Three field surveys were performed. Data were acquired with a standard bottom deployed refraction seismic hydrophone array containing 24 or 48 receivers, with a receiver spacing of 2.5 m. Explosive charges were used as sources. The recording time was increased from 0.5 to 8 s, ...
1998-12-31
Energy Technology Data Exchange (ETDEWEB)
By means of neutron diffraction, using the standard polycrystalline sample of Al{sub 2}O{sub 3}, measurements on three (of four spectrometers) already installed in the front of horizontal channels of MARIA reactor have been performed. Basing on these experiments as well as on activation measurements carried out earlier, the fluxes of monoenergetic neutrons have been estimated. These experiments allowed to determine (for a given geometry and kind of monochromators chosen) the resolution efficiency of instruments and high order contamination in the reflected beam. With the help of polycrystalline vanadium and TbBr{sub 3} sample, the possibility of studies using the inelastic scattering process have been tested. (author) 7 refs, 15 figs, 7 tabs
1997-12-31
British Library Electronic Table of Contents (United Kingdom)
Background: Ecchymosis, oedema, haematoma and pain after SMAS-based facelift surgery are all the direct result of the physical trauma of surgery and subsequent inflammatory response. Hilotherapy is a novel form of cryotherapy that purports to minimise these events through single-use face masks circulating cooled, sterile water. This study was performed to assess the validity of Hilotherapy in this population of patients. Methods: Over 14 weeks fifty consecutive patients were randomised to post-operative facial cooling with Hilotherapy or management with standard dressings alone, while fifteen subsequent, consecutive patients were randomised to cooling of one side of the face but not the other. Assessment of ecchymosis, oedema, haematoma and pain was performed independently by clinical staf...
2011-01-01
British Library Electronic Table of Contents (United Kingdom)
Since the end of the 1990s, good quality lighting was that which balanced the needs of humans, economic and environmental issues, and architectural design. Recent studies aimed to find a correlation between environmental lighting and human performance and health, with positive results. What is known, is that insufficient or inappropriate light exposure can disrupt standard human rhythms which may result in adverse consequences for performance, safety, health. By studying the relationship between human physiology and light, research in photobiology has advanced to the point where some attempts to foresee what the lighting practice will be in future. The question is if lighting practice and lighting practitioners are ready for changes. This paper has the aim of introducing the recent discove...
2011-01-01
Energy Technology Data Exchange (ETDEWEB)
The gastrointestinal transit was studied in 20 patients with loop transverse colostomies and previously normal colons. This analysis was performed through radiological observation of progression of 20 radiopaque pellets and measurements of its transit time in the various segments of the digestive tract. An evaluation of other related clinical and radiological events was carried out sentimentality's. In order to better understand the influence of the surgical procedure, the study was performed under similar dietary and supportive care conditions and standard radiological studies before and after the re-establishment of transit, thus enabling a comparison with the same individual. (author)
1988-07-01
Flue-gas desulfurization inspection and performance evaluation. Manual
Energy Technology Data Exchange (ETDEWEB)
The intent of this manual is to provide inspectors from Federal and state environmental agencies with information regarding the problems that plague lime/limestone slurry flue-gas desulfurization (FGD) systems that will aid them in their inspections and performance evaluations of these systems with respect to compliance with the emission standards that have evolved since the passage of the 1970 Clean Air Act. A unique feature of the manual is its structure as a tool, or working document, which will accompany the inspector on each plant inspection. Thus, the document is presented in user friendly fashion and tailored to provide practical information for its intended use--to assist in the systematic inspection of an FGD system to determine present and future compliance status. The approach entails the use of nomographs, checklists, matrices, simplified diagrams, cross-referencing, and indexing of textual information, and the presentation of ...
1985-10-01
British Library Electronic Table of Contents (United Kingdom)
The primary objective of batch data as trajectory alignment (or synchronization) is to standardize the data sampling per batch according to the evolution of the process, and secondarily to homogenize the samples per run. The use of an indicator variable performs both objectives well. Two examples from the pharmaceutical sector are discussed to illustrate the different ways to deal with uneven samples across batches and across variables in the same batch. Since trajectory alignment requires large time investment, a simple triage approach is proposed to assess the need to analyze the dynamics of a given process and hence perform alignment. The presented examples are representative of a broad variety of batch processes that are operated by recipe in the pharmaceutical sector. In our experienc...
2011-01-01
Comparison of laparoscopic transabdominal lateral versus posterior retroperitoneal adrenalectomy
British Library Electronic Table of Contents (United Kingdom)
Background For the past 14 years, we have been performing laparoscopic adrenalectomy via the lateral transabdominal as well as the posterior retroperitoneal approach. The aim of this study is to describe patient selection criteria for each approach with comparison of perioperative outcomes. Methods In patients with smaller tumors, low body mass index (BMI), history of previous abdominal operations, appropriate body habitus, and bilateral pathology, we have performed preferentially the posterior approach. Data regarding clinical pathology, tumor size, BMI, estimated blood loss (EBL), operating time (OT), morbidity, mortality, and duration of stay were analyzed retrospectively. Data are expressed as mean +- standard error of the mean (SEM). Results One hundred seventy-two laparoscopic adrena...
2009-01-01
Comparative evolution of various CCD image sensors hardening techniques with ionizing radiation
International Nuclear Information System (INIS)
This paper reviews various techniques to harden Charged Coupled Device (CCD) sensors and the results after irradiation of three Thomson n buried channel CCDs having a different degree of hardening. It describes the major irradiation effects on CCD performances and it makes a comparison of the results between the different hardening levels. It shows good results on dark voltage after ionizing radiation for TH 7863M device hardened both by design and by operating conditions (MPP mode) with respect to the standard device TH 7863A. The irradiations were performed with "6"0Co or X-ray (10 keV) sources on devices in operating mode. (author). 3 refs., 8 figs.
Achieving a vanishing SNR-gap to exact lattice decoding at a subexponential complexity
The work identifies the first lattice decoding solution that achieves, in the general outage-limited MIMO setting and in the high-rate and high-SNR limit, both a vanishing gap to the error-performance of the (DMT optimal) exact solution of preprocessed lattice decoding, as well as a computational complexity that is subexponential in the number of codeword bits. The proposed solution employs lattice reduction (LR)-aided regularized (lattice) sphere decoding and proper timeout policies. These performance and complexity guarantees hold for most MIMO scenarios, all reasonable fading statistics, all channel dimensions and all full-rate lattice codes. In sharp contrast to the above manageable complexity, the complexity of other standard preprocessed lattice decoding solutions is shown here to be extremely high. Specifically the work is first to quantify the complexity of these lattice (sphere) decoding solutions and to prove the ...
2011-01-01
Summary of Information and Resources Related to Energy Use in Healthcare Facilities - Version 1
Energy Technology Data Exchange (ETDEWEB)
This document presents the results of a review of publicly available information on energy use in health care facilities. The information contained in this document and in the sources cited herein provides the background and context for efforts to reduce energy use and costs in health care. Recognizing the breadth and diversity of relevant information, the author acknowledges that the report is likely not comprehensive. It is intended only to present a broad picture of what is currently known about health care energy use. This review was conducted as part of a 'High Performance Health Care Buildings' research study funded by the California Energy Commission. The study was motivated by the recognition that health care facilities collectively account for a substantial fraction of total commercial building energy use, due in large part to the very high energy intensity of hospitals and other inpatient care ...
2009-09-08
D & D screening risk evaluation guidance
Energy Technology Data Exchange (ETDEWEB)
The Screening Risk Evaluation (SRE) guidance document is a set of guidelines provided for the uniform implementation of SREs performed on decontamination and decommissioning (D&D) facilities. Although this method has been developed for D&D facilities, it can be used for transition (EM-60) facilities as well. The SRE guidance produces screening risk scores reflecting levels of risk through the use of risk ranking indices. Five types of possible risk are calculated from the SRE: current releases, worker exposures, future releases, physical hazards, and criticality. The Current Release Index (CRI) calculates the current risk to human health and the environment, exterior to the building, from ongoing or probable releases within a one-year time period. The Worker Exposure Index (WEI) calculates the current risk to workers, occupants and visitors inside contaminated D&D ...
1995-09-01
Standards and guidances for limiting ionizing radiation exposure
Energy Technology Data Exchange (ETDEWEB)
This chapter is concerned with standards and guidances for limiting radiation exposures. It is divided into three sections, each of which has several parts. Section 1: Ionizing Radiation -- Standards and Guidances Applicable to the Public: Part A, Radiation Protection Standards; Part B, Environmental Radiation Standards; Part C, Exempt Levels of Radioactivity; Part D, Protective Action Guides for Accidents. Section 2: Ionizing Radiation -- Standards Applicable to the Workplace. Section 3: Medical and Other Standards.
1992-12-31
On new methods for standardization of samples in activation analysis of biological materials
International Nuclear Information System (INIS)
New standardization techniques of samples in multielement instrumental neutron-activation analysis (INAA) of biological materials (BM) are considered. New methodical developments of sample preparation techniques, BM tableting, creation of comparison standards and standardization of packing material are suggested. Correlated data on concentration of different elements in standard specimens-comparison standards are presented for mass INAA, that is: for phenol-formaldehyde resin-base and human blood-base synthetic standards. 7 refs.; 3 tabs.
1988-06-26
Indian Academy of Sciences (India)
central server with search facility involving all partner journals ...
Energy Technology Data Exchange (ETDEWEB)
As part of the work scope set in the French law on high level long lived waste R&D passed in 1991, CEA is conducting a research program to establish the scientific basis and assess the feasibility of long term storage as an option for the safe management of nuclear waste for periods as long as centuries. This goal is a significant departure from the current industrial practice where storage facilities are usually built to last only a few decades. From a technical viewpoint such an extension in time seems feasible provided care and maintenance is exercised. Considering such long periods of time, the risk for Society of loosing oversight and control of such a facility is real, which triggers the question of whether and how long term storage safety can be actually achieved. Therefore CEA commissioned a study (1) in which MUTADIS Consultants (2) and CEPN (3) were both involved. The case study looks into several past and actual human ...
2003-02-24
Analysis of a Fast Spectrum Irradiation Facility in the High Flux Isotope Reactor
Energy Technology Data Exchange (ETDEWEB)
The Global Nuclear Energy Partnership (GNEP) is proposing to develop a sodium-cooled fast-spectrum reactor (SFR) to transmute and consume actinides from discharged nuclear fuel. To meet performance objectives, new and advanced fuels and targets need to be developed. The fuels to be irradiated include metal and oxide mixed actinides (U-Np-Pu-Am-Cm); for the target concept, Am-Cm has been considered. A significant part of the development process is the irradiation of the fuel and cladding in a prototypic fast reactor environment to determine the performance under irradiation. Analysis results are presented in this paper for a fast-neutron irradiation facility design based on the large fast neutron flux available in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) combined with the use of a strongly-absorbing thermal neutron shield. Several designs were assessed; the preferred concept consists of a ...
2008-09-01
Glass Furnace Combustion and Melting Research Facility.
Energy Technology Data Exchange (ETDEWEB)
The need for a Combustion and Melting Research Facility focused on the solution of glass manufacturing problems common to all segments of the glass industry was given high priority in the earliest version of the Glass Industry Technology Roadmap (Eisenhauer et al., 1997). Visteon Glass Systems and, later, PPG Industries proposed to meet this requirement, in partnership with the DOE/OIT Glass Program and Sandia National Laboratories, by designing and building a research furnace equipped with state-of-the-art diagnostics in the DOE Combustion Research Facility located at the Sandia site in Livermore, CA. Input on the configuration and objectives of the facility was sought from the entire industry by a variety of routes: (1) through a survey distributed to industry leaders by GMIC, (2) by conducting an open workshop following the OIT Glass Industry Project Review in September 1999, (3) from discussions with numerous glass ...
2004-08-01
The stability of biological standards
UK PubMed Central (United Kingdom)
The authors emphasize the importance of stability in biological standards and discuss the steps taken to ensure the stability of International Standards and the theoretical basis of the various stability...Full Text Available
1956-01-01
Standardization of Ajmodadi churna, a polyherbal formulation
UK PubMed Central (United Kingdom)
Standardization of herbal formulations is essential in order to assess the quality of drugs, based on the concentration of their active principles. This article reports on standardization of Ajmodadi...Full Text Available
2010-03-01
Ada Compiler Validation Summary Report: Certificate Number ...
... Standards Validation Group National Computer Systems Laboratory National Institute of Standards and Technology ... STANDARD. ... (See test Ci )i3A. ...
1989-08-18
ESBWR related passive decay heat removal tests in PANDA
International Nuclear Information System (INIS)
A number of test series to investigate passive safety systems for the next generation of Light Water Reactors have been performed in the PANDA multi-purpose facility at the Paul Scherrer Institut (PSI). The large scale thermal-hydraulic test facility allows to investigate LWR containment phenomena and system behaviour. PANDA was first used to examine the Passive Containment Cooling System (PCCS) for the Simplified Boiling Water Reactor (SBWR). In 1996 new test series were initiated; all related to projects of the EC Fourth Framework Programme on Nuclear Fission Safety. One of these projects (TEPSS) is focused on the European Simplified Boiling Water Reactor (ESBWR). The ESBWR containment features and PCCS long-term post LOCA response were investigated in PANDA. The PCCS start-up was demonstrated, the effect of nitrogen hidden somewhere in the drywell and released later in the transient was simulated and the effect of light ...
1999-04-19
Energy Technology Data Exchange (ETDEWEB)
Worker exposures to N-nitroso compounds were evaluated at B.F. Goodrich Company, Woodburn, Indiana on December 12, 1979. Personal and area air samples were collected and analyzed by gas-chromatography and thermal-energy-analysis methods. All of the samples contained N-nitrosomorpholine (NMOR) and five samples also contained N-nitrosodimethylamine (NDMA). The amount of NMOR ranged from 0.85 to 3.7 micrograms per cubic meter (micrograms/cu m) for area air samples and 0.63 to 1.8 micrograms/cu m for personal samples. NDMA concentrations ranged from undetectable to 1.8 microgram/cu m for area samples and undetectable to 0.09 micrograms/cu m for personal samples. The authors note that no exposure standards exist for NDMA or NMOR but both are listed as potential human carcinogens. They suggest that the B.F. Goodrich Company characterize nitrosamine exposures at this facility.
1980-02-28
OZONE PRODUCTION IN THE PHILADELPHIA URBAN AREA DURING NE-OPS 99
International Nuclear Information System (INIS)
As part of the 1999 NARSTO Northeast Oxidant and Particulate Study (NE-OPS) field campaign, the DOE G-1 aircraft sampled trace gases and aerosols in and around the Philadelphia metropolitan area. Twenty research flights were conducted between July 25 and August 11. The overall goals of these flights were to obtain a mechanistic understanding of O(sub 3) production; to characterize the spatial and temporal behavior of photo-oxidants and aerosols; and to study the evolution of aerosol size distributions, including the process of new particle formation. Within the NE-OPS program, other groups provided additional trace gas, aerosol, and meteorological observations using aircraft, balloon, remote sensing, and surface based instruments (Phillbrick et al., 2000). In this article we provide an overview of the G-1 observations related to O(sub 3) production, focusing on the vertical distribution of pollutants. Ozone production rates are calculated using a box model that is constrained by ...
Intense negative-ion beams extracted from an ECR ion source coupled to a charge exchange canal
Energy Technology Data Exchange (ETDEWEB)
Electron cyclotron resonance (ECR) ion sources possess several advantages over ion sources conventionally used for injectors of electrostatic accelerators: improved reliability, high efficiency, simplicity, and the capability of generating bright, high-current ion beams. We have adapted a high-current ECR source originally developed as an injector for a CW RFQ proton linac to serve as a source of intense negative-ion beams for the Tandem Accelerator Superconducting Cyclotron (TASCC) facility at Chalk River. The range of ion species of the source has been extended from H{sup 1+} alone up to Bi{sup 1+}, with both gaseous and nonvolatile feeds. Two intense negative-ion beams of He{sup -} and O{sup -} have been generated so far with the source coupled to a standard charge-exchange canal. We foresee no major problems generating a broad range of negative ions with this system. (author)
1993-07-01
Intense negative-ion beams extracted from an ECR ion source coupled to a charge exchange canal
International Nuclear Information System (INIS)
Electron cyclotron resonance (ECR) ion sources possess several advantages over ion sources conventionally used for injectors of electrostatic accelerators: improved reliability, high efficiency, simplicity, and the capability of generating bright, high-current ion beams. We have adapted a high-current ECR source originally developed as an injector for a CW RFQ proton linac to serve as a source of intense negative-ion beams for the Tandem Accelerator Superconducting Cyclotron (TASCC) facility at Chalk River. The range of ion species of the source has been extended from H1+ alone up to Bi1+, with both gaseous and nonvolatile feeds. Two intense negative-ion beams of He- and O- have been generated so far with the source coupled to a standard charge-exchange canal. We foresee no major problems generating a broad range of negative ions with this system. (author)
1993-09-22
Energy Technology Data Exchange (ETDEWEB)
This is the eighth part of a ten-part final report for the Swiss Federal Office of Energy (SFOE) on a project that looked into potential problems relating to the Swiss electricity distribution grid with respect to the increasing number of distributed power generation facilities being put into service. The identification of special conditions for the grid's operation and future development that take increasing decentralised power production into account are discussed. The results of the project activities encompass the analysis and evaluation of various problem areas associated with planning and management of the grid during normal operation and periods of malfunction, as well as required modifications to safety systems and grid configurations. This seventh appendix to the main report summarises and discusses the knowledge gained during the project and attempts to provide answers to various questions posed by the use of distributed power generation in ...
2003-07-01
Future Accelerators, Muon Colliders, and Neutrino Factories
Energy Technology Data Exchange (ETDEWEB)
Particle physics is driven by five great topics. Neutrino oscillations and masses are now at the fore. The standard model with extensions to supersymmetry and a Higgs to generate mass explains much of the field. The origins of CP violation are not understood. The possibility of extra dimensions has raised tantalizing new questions. A fifth topic lurking in the background is the possibility of something totally different. Many of the questions raised by these topics require powerful new accelerators. It is not an overstatement to say that for some of the issues, the accelerator is almost the experiment. Indeed some of the questions require machines beyond our present capability. As this volume attests, there are parts of the particle physics program that have been significantly advanced without the use of accelerators such as the subject of neutrino oscillations and many aspects of the particle-cosmology interface. At this stage in the development of physics, both ...
2001-12-19
Fluid mixing in reactor containment
Energy Technology Data Exchange (ETDEWEB)
Full text of publication follows: Hydrogen release and distribution in nuclear power plant containment is an important safety issue. Selection of a proper turbulence model is important for accurate estimation of the mixing process. The selection of turbulence model is dictated by the best compromise between accuracy and computational efforts. For this, three different turbulence models, viz. Standard k-{epsilon}, RNG k-{epsilon} and Reynolds Stress Model, based on Reynolds averaged Navier Stokes equations (RANS) approach, were used. The computations were done using the CFD code FLUENT, which is based on the control volume methodology. The computational results were compared with the experimental results of HYMIS test facility, where helium was used to simulate hydrogen. The processes of helium plume rise, multiple plume merging, distribution and mixing were studied. Based on these computations, a simple analytical/empirical zone based model was ...
2005-07-01
Fluid mixing in reactor containment
International Nuclear Information System (INIS)
Full text of publication follows: Hydrogen release and distribution in nuclear power plant containment is an important safety issue. Selection of a proper turbulence model is important for accurate estimation of the mixing process. The selection of turbulence model is dictated by the best compromise between accuracy and computational efforts. For this, three different turbulence models, viz. Standard k-#epsilon#, RNG k-#epsilon# and Reynolds Stress Model, based on Reynolds averaged Navier Stokes equations (RANS) approach, were used. The computations were done using the CFD code FLUENT, which is based on the control volume methodology. The computational results were compared with the experimental results of HYMIS test facility, where helium was used to simulate hydrogen. The processes of helium plume rise, multiple plume merging, distribution and mixing were studied. Based on these computations, a simple analytical/empirical zone based model was ...
2005-10-02
Environmental Restoration Program quality assurance system requirements for the Hanford Site
International Nuclear Information System (INIS)
This document defines the quality assurance program requirements for the US Department of Energy, Richland Field Office, Environmental Restoration program at the Hanford Site. This document integrates quality assurance requirements from US Department of Energy Orders, the Hanford Federal Facility Agreement and Consent Order, and applicable industry standards into a single source document for the development of quality assurance programs applicable to the Environmental Restoration program items and activities. This document has been configured into three parts and fifteen criteria to provide user organizations with a workable document that best facilitates line operations. When developing individual user organization quality assurance programs, the document configuration provides each organization with the Flexibility to incorporate only those parts and criteria that are applicable to their individual scope of work as it is associated with the ...
Energy Technology Data Exchange (ETDEWEB)
The 'high-tension distribution line design support system' was developed for the 'work design support system'. This support system is composed of the work outline editor for preparing work details and facility data and the inference engine for preparing practical design plans, and can check system conditions such as voltage drop and deviation from technical standards automatically. The work outline editor takes charge of selection of work items, selective input of system information, and setting of some conditions such as pole position and reserved load onto a system diagram. The inference engine provides the design plan automatically based on the information inputted by the editor. For the design of high-tension distribution line, such various factors as local condition and load sharing of distribution systems should be considered. This design support system attains efficient processing by not total ...
2000-02-10
Analysis of High-Moderation MOX Core MISTRAL-3 with SRAC and MVP
International Nuclear Information System (INIS)
To obtain reactor physics parameters for high-moderation mixed-oxide (MOX) cores, Nuclear Power Engineering Corporation (NPEC), the French Atomic Commission (CEA), and their industrial partners have conducted a MOX core physics experimental program called MISTRAL with the EOLE critical facility of the Cadarache research center. This program consists of four high-moderation cores and was successfully completed in July 2000. This paper describes the analysis results of MISTRAL-3 that is a homogeneous full MOX cylindrical core (H/HM = 6.2) with an 80-cm height and a 59-cm diameter consisting of 1388 standard pressurized water reactor-type MOX fuel rods of 7.0 wt% plutonium-enrichment in a square pitch of 1.39 cm. NPEC has been analyzing the experimental results by using the SRAC and MVP code systems. SRAC and MVP calculate the nuclear core characteristics correctly for the high-moderation MOX core MISTRAL-3. No apparent trend with the moderation ...
2001-06-17
British Library Electronic Table of Contents (United Kingdom)
Abstract BACKGROUND: Nitrate leaching and the resulting groundwater contamination from intensive cereal production has become a major concern for long-term farmland efficiency and environmental sustainability in northern China. The aim of this study was to evaluate a water-saving super-absorbent polymer (SAP) for minimising NO3- leaching from soil and optimising corn growth and yield. Thirty-six undisturbed soil lysimeters were installed in a field lysimeter facility in drought-affected northern China to study the growth and yield characteristics of summer corn (Zea mays L.) as well as the amount of NO3-leaching losses under different fertiliser (standard, medium or 75% and low, or 50% of conventional fertilisation rate) and SAP (control, 0; level-1, 15 kg ha-1 and level-2, 30 kg ha-1) tre...
2011-01-01
This report presents the operating results for Run 245 at the Advanced Coal Liquefaction R and D Facility in Wilsonville, Alabama. This run was made in an all-distillate Integrated Two-Stage Liquefaction (ITSL) mode using Illinois 6 coal from the Burning Star mine. The primary run objective was to obtain steady-state ITSL performance by replacing spent HTR reactor catalyst with fresh, sulfided catalyst. Secondary objectives were to maintain an all-distillate (minimum resid production) product slate and to demonstrate the effects of catalyst addition on the net gas production and hydrogen consumption. Run 245 began on 7 November, 1983, and continued through 12 February, 1984. During this period, 179.0 tons of coal was fed in 2045 hours of operation. Eight special product workup material balances were defined, and the results are presented herein. 6 references, 28 figures, 20 tables.
1984-10-01
Verification of maximum impact force for interim storage cask for the Fast Flux Testing Facility
Energy Technology Data Exchange (ETDEWEB)
The objective of this paper is to perform an impact analysis of the Interim Storage Cask (ISC) of the Fast Flux Test Facility (FFTF) for a 4-ft end drop. The ISC is a concrete cask used to store spent nuclear fuels. The analysis is to justify the impact force calculated by General Atomics (General Atomics, 1994) using the ILMOD computer code. ILMOD determines the maximum force developed by the concrete crushing which occurs when the drop energy has been absorbed. The maximum force, multiplied by the dynamic load factor (DLF), was used to determine the maximum g-level on the cask during a 4-ft end drop accident onto the heavily reinforced FFTF Reactor Service Building`s concrete surface. For the analysis, this surface was assumed to be unyielding and the cask absorbed all the drop energy. This conservative assumption simplified the modeling used to qualify the cask`s structural integrity for this accident condition.
1996-06-01
International Nuclear Information System (INIS)
This paper presents actual time/motion data for an oversize truck spent-fuel shipment from its origin, Surry, Virginia to its destination, Idaho National Engineering Laboratory (INEL). These data include the receipt of the empty cask at the reactor, wet-loading the cask, over-the-road or in-transit data, and receipt and dry unloading of the shipping cask at the receiving facility. Occupational doses were recorded at the Surry Power Plant as well as at INEL, and public doses were calculated for the in-transit dose analysis. This shipment was one of a series performed in support of a demonstration and evaluation of dry storage at INEL. The oversized shipment consisted of a TN-8L shipping cask loaded with three 10-yr-old pressurized water reactor assemblies. The total distance traveled was #approx#2800 miles, requiring 62 h including stops. The time required to receive and inspect the empty shipping cask and wet-load and release the shipment at ...
1988-11-04
Tiger Team assessment of the Brookhaven National Laboratory
Energy Technology Data Exchange (ETDEWEB)
This report documents the results of the Department of Energy's (DOE's) Tiger Team Assessment conducted at Brookhaven National Laboratory (BNL) in Upton, New York, between March 26 and April 27, 1990. The BNL is a multiprogram laboratory operated by the Associated Universities, Inc., (AUI) for DOE. The purpose of the assessment was to provide the status of environment, safety, and health (ES H) programs at the laboratory. The scope of the assessment included a review of management systems and operating procedures and records; observations of facility operations; and interviews at the facilities. Subteams in four areas performed the review: ES H, Occupational Safety and Health, and Management and Organization. The assessment was comprehensive, covering all areas of ES H activities and waste management operations. Compliance with applicable Federal, State, and local regulations; applicable DOE Orders; and ...
1990-06-01
Status Report of Simulated Space Radiation Environment Facility
Energy Technology Data Exchange (ETDEWEB)
The technology for performance testing and improvement of materials which are durable at space environment is a military related technology and veiled and securely regulated in advanced countries such as US and Russia. This core technology cannot be easily transferred to other country too. Therefore, this technology is the most fundamental and necessary research area for the successful establishment of space environment system. Since the task for evaluating the effects of space materials and components by space radiation plays important role in satellite lifetime extension and running failure percentage decrease, it is necessary to establish simulated space radiation facility and systematic testing procedure. This report has dealt with the status of the technology to enable the simulation of space environment effects, including the effect of space radiation on space materials. This information such as the fundamental knowledge of space ...
2007-11-15
International Nuclear Information System (INIS)
The paper discusses the safety problems connected with the conversion to dense storage of RBMK-1000 spent fuel in reactor cooling pools and independent storage facilities. Recourse to dense storage has been made for a number of reasons, among which are the absence of spent fuel shipments from the nuclear power plant site, prolongation of storage time and a partial change in storage conditions. Increasing the storage density per unit volume of the storage facility and turning to new technical procedures (as against the basic design) call for further investigation of safety problems. The safety assessment of the dense storage mode includes: (1) Selecting a list of initiating events for design basis and unforeseeable accidents; (2) Assessing dense storage safety under normal as well as design basis accident conditions; (3) Safety analysis and development of measures to compensate for unforeseen accidents. Based on the studies ...
1995-08-01
Power Systems Development Facility Gasification Test Campaign TC17
Energy Technology Data Exchange (ETDEWEB)
In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama, routinely demonstrates gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a KBR (formerly Kellogg Brown & Root) Transport Gasifier, a hot gas particulate control device, advanced syngas cleanup systems, and high-pressure solids handling systems. This report summarizes the results gasification operation with Illinois Basin bituminous coal in PSDF test campaign TC17. The test campaign was completed from October 25, 2004, to November 18, 2004. System startup and initial operation was accomplished with Powder River Basin (PRB) subbituminous coal, and then the system was transitioned to Illinois Basin coal operation. The major objective for this test ...
2004-11-30
NATIONAL HIGH MAGENTIC FIELD LABORATORY FEL INJECTOR DESIGN CONSIDERATION
Energy Technology Data Exchange (ETDEWEB)
A Numerical study of beam dynamics was performed for two injector systems for the proposed National High Magnetic Field Laboratory at the Florida State University (FSU) Free Electron Laser (FEL) facility. The first considered a system consisting of a thermionic DC gun, two buncher cavities operated at 260 MHz and 1.3 GHz and two TESLA type cavities, and is very similar to the injector of the ELBE Radiation Source. The second system we studied uses a DC photogun (a copy of JLab FEL electron gun), one buncher cavity operated at 1.3 GHz and two TESLA type cavities. The study is based on PARMELA simulations and takes into account operational experience of both the JLab FEL and the Radiation Source ELBE. The simulations predict the second system will have a much smaller longitudinal emittance. For this reason the DC photo gun based injector is preferred for the proposed FSU FEL facility.
2007-06-25
Measures for reliability improvement of on-site power plant at steel works
Energy Technology Data Exchange (ETDEWEB)
This report describes the arrangement and features of the Ogishima thermal power plant facilities, as well as activities being performed there for operation control, regular inspection and improvement in reliability. The power plant uses about 48 percent of the by-product gas as its fuel to supply about 81 percent of the required power. Operation of the No. 1 unit started in 1976. Currently, the plant has three units, each with an output of 125MW. Each unit consists of a natural circulation boiler with a maximum evaporation capacity of 410 ton/hour and a reheat regenerative condensing turbine with a main vapor pressure of 127 kg/cm/sup 2/G. Techniques used for water properties control and combustion control are also described. In the plant, convetional time management integrity techniques are now being replaced by state management integrity techniques that determines the deterioration tendency in separate sections of the ...
1988-04-15
Maintenance Implementation Plan for solid waste
Energy Technology Data Exchange (ETDEWEB)
This Maintenance Implementation Plan (MIP) has been developed for. implementation of the US Department of Energy (DOE) Order 4330.4A. Maintenance Implementation Program (DOE 1990) at the Hanford Site Solid Waste complex. It addresses maintenance functions associated with Solid Waste Management, which includes the field operational group and the facilities operational group. An assessment of the existing maintenance programs for Solid Waste was performed, and the results of this assessment were evaluated to determine corrective actions required to bring Solid Waste Maintenance into compliance with the order. The MIP assessment disclosed that most elements defined in the order are currently implemented for Solid Waste. It also identified issues which must be addressed to bring the maintenance function into full compliance with DOE Order 4330.4A. These include documentation of the maintenance training program, expanded scope of inspections to ...
1992-06-01
Fuel management at the Petten high flux reactor
Energy Technology Data Exchange (ETDEWEB)
Several years ago the shipment of spent fuel of the High Flux Reactor (HFR) at Petten has come to a standstill resulting in an ever growing stock of fuel elements that are labelled 'fully burnt up'. Examination of those elements showed that a reasonably number of them have a relatively high {sup 235}U mass left. A reactor physics analysis showed that the use of such elements in the peripheral core zone allows the loading of four instead of five fresh fuel elements in many cycle cores. For the assessment of safety and performance parameters of HFR cores a new calculational tool is being developed. It is based on AEA Technology's Reactor physics code suite Winfrith Improved Multigroup Scheme (WIMS). NRG produced pre- and post-processing facilities to feed input data into WIMS's 2D transport code CACTUS and to extract relevant parameters from the output. The processing facilities can be used ...
1999-07-01
Energy Technology Data Exchange (ETDEWEB)
Although the Federal Facility Agreement (FFA) addresses the entire Oak Ridge Reservation, specific requirements are set forth for the liquid low-level radioactive waste (LLLW) storage tanks and their associated piping and equipment, tank systems, at ORNL. The stated objected of the FFA as it relates to these tank systems is to ensure that structural integrity, containment and detection of releases, and source control are maintained pending final remedial action at the site. The FFA requires that leaking LLLW tank systems be immediately removed from service. It also requires the LLLW tank systems that do not meet the design and performance requirements established for secondary containment and leak detection be either upgraded or replaced. The FFA establishes a procedural framework for implementing the environmental laws. For the LLLW tank systems, this framework requires the specified plans and schedules be submitted to EPA and TDEC for ...
1992-03-01
Fast Flux Test Facility reactor initial criticality predictions and measurements
International Nuclear Information System (INIS)
The Fast Flux Test Facility (FFTF) was designed to test fast-reactor fuels and other nonfuel materials. In its 37 reactor cycles of operations, the FFTF reactor has performed very well and successfully completed all the irradiation testings with an operating efficiency factor as high as 98%. Since FFTF is an experimental reactor, its core loading changed from cycle to cycle. Depending on the number of test assemblies in the core and their location, the core loading can change significantly from an essentially homogeneous core loading to a relatively nonhomogeneous or even highly localized heterogeneous loading. Consequently, the core reload design and initial criticality analyses were required for each operating cycle. The zero power initial critical control rod bank height was predicted before each reactor startup. The initial critical prediction depends on the reactivity conditions at the end of the previous cycle, the temperature feedback ...
1992-06-07
FFTF [Fast Flux Test Facility] fuel handling experience (1979--1986)
International Nuclear Information System (INIS)
The Fast Flux Test Facility (FFTF)is a 400 MW (th) sodium-cooled fast flux test reactor located on the Hanford Site in southeastern Washington State. The FFTF is operated by the Westinghouse Hanford Company for the United States Department of Energy. The FFTF is a three loop plant designed primarily for the purpose of testing full-scale core components in an environment prototypic of future liquid metal reactors. The plant design emphasizes features to enhance this test capability, especially in the area of the core, reactor vessel, and refueling system. Eight special test positions are provided in the vessel head to permit contact instrumented experiments to be installed and irradiated. These test positions effectively divide the core into three sectors. Each sector requires its own In-Vessel Handling Machine (IVHM) to access all the core positions. Since the core and the in-vessel refueling components are submerged under sodium, all handling operations must be ...
1987-09-01
Energy Technology Data Exchange (ETDEWEB)
Previous laboratory tests of elastomer O-rings in coal liquefaction solvents conducted at L'Garde, Inc., indicated that certain ethylenepropylenediene monomer (EPDM) compounds provided the best performance when a backup ring was used to limit swelling. Before service testing in a pump at the Wilsonville, Alabama, Advanced Coal Liquefaction Research and Development Facility, tests of six selected elastomers in the appropriate Wilsonville-produced solvent were conducted at Oak Ridge National Laboratory (ORNL). The ORNL tests measured the elastomers' changes in cross section, weight, density, and relative flexibility. Although two perfluoroelastomers showed less degradation of most properties during these tests, it was decided to proceed with service testing of two EPDM elastomers because of their much lower cost. 5 refs., 14 figs., 7 tabs.
1986-08-01
Drop Test of the Candu Spent Fuel Storage Basket in MACSTOR/KN-400
International Nuclear Information System (INIS)
The MACSTOR/KN-400 of Wolsung power plant in Korea is a dry interim storage facilities. There are 400 long slender cylinders in MACSTOR/KN-400. In one cylinder, ten baskets where Candu spent fuels are loaded are stacked and stored. For this MACSTOR/KN-400 facilities, analyses and tests for the hypothetical accident conditions that might happen during moving and storing baskets into a cylinder were performed. The hypothetical accident conditions to be considered are two cases. One is the case of basket dropping onto the bottom plate of a cylinder. The other is the case of basket dropping onto the other basket top plate stored in the cylinder. For the drop analyses, the case of hanging cylinder and the case of cylinder on the unyielding target surface were considered. Based on the dropping analysis, testing condition was determined as the latter case that is for the cylinder on the target surface. In a basket, 60 dummy fuel ...
2009-06-01
Development of real time personal neutron dosimeter with two silicon detectors
Energy Technology Data Exchange (ETDEWEB)
The personal neutron dosimetry becomes more important with the increasing use of nuclear and accelerator facilities. The solid state track detector, film badge and thermo-luminescent dosimeter have widely been used as passive-type personal neutron dosimeters, but the real-time neutron dosimeter is strongly needed. A real time personal dosimeter which could give neutron dose equivalent over wide energy range from thermal to 10 odd MeV by using two neutron sensors has been developed by our group. For practical commercial product, some changes from these prototype sensors have recently been done by Fuji Electric Co. Ltd. The purpose of this work is the final performance test of the dosimeter just before sale. We checked again about the sensitivity in the monoenergetic neutron field from 8 keV to 15 MeV and in the neutron fields around a few accelerator facilities. (author)
1997-07-01
Design experience of the JRR-2 BNCT facility in JAERI
Energy Technology Data Exchange (ETDEWEB)
The thermal neutron column of the JRR-2 reactor was remodelled in order to install a medical irradiation facility. The design experience and the cource of this remodelling are presented. At first, the thermal neutron flux was lower than expected, and the expected radiation condition was achieved by the following improvements: (1) removal of graphite from the thermal neutron column to increase the neutron flux, (2) twice increase of bismuth shielding and the shift of its position to improve the shielding effect against gamma ray, (3) application of B{sub 4}C rubber on the both surfaces of the shielding door to suppress the secondary gamma ray generation from the structural materials, (4) LiF tiles are applied on the inner face of the neutron beam exit hole to suppress the secondary gamma ray from the beam exit, and (5) installment a cone-shape polyethylene collimator to relieve the decay of thermal neutron. After the improvements, medical irradiation treatments have ...
1994-06-01
CFD Analysis of a Dry Storage System for MACSTOR/KN-400
International Nuclear Information System (INIS)
There are four nuclear power plants in operation at Wolsong and, annually, more than 5,000 assemblies of spent nuclear fuels are released from each plant. Thus the concrete silo type dry storage system was constructed from '90. However, after 2006, another dry storage facility is required to accept the all amount of spent nuclear fuels from the plants. Instead of the concrete silo type, MACSTOR/KN-400 was developed to store the CANDU spent nuclear fuel more densely. In this study, computational fluid dynamics (CFD) analysis of the MACSTOR/KN-400 model was performed to confirm the thermal integrity of the facility, especially for the concrete structure, using the commercial CFD code, FLUENT. The MACSTOR/KN-400 which has Thermal Insulation Panel (TIP) and IAEA Re-verification Pipe (RVP) was modeled and analyzed in the view point of the thermal integrity of the concrete structure.
2007-10-01
Energy Technology Data Exchange (ETDEWEB)
A numerical model of multiphase air-water flow and contaminant transport in the unsaturated zone is presented. The multiphase flow equations are solved using the two-pressure, mixed form of the equations with a modified Picard linearization of the equations and a finite element spatial approximation. A volatile contaminant is assumed to be transported in either phase, or in both phases simultaneously. The contaminant partitions between phases with an equilibrium distribution given by Henry`s Law or via kinetic mass transfer. The transport equations are solved using a Galerkin finite element method with reduced integration to lump the resultant matrices. The numerical model is applied to published experimental studies to examine the behavior of the air phase and associated contaminant movement under water infiltration. The model is also used to evaluate a hypothetical design for a low-level radioactive waste disposal facility. The model has been developed in both ...
1995-05-01
XRF analysis of rock and sediment using standard rock samples
Energy Technology Data Exchange (ETDEWEB)
A simple and rapid method is described for the determination of major and trace elements in rock and sediment samples by wavelength dispersive XRF. Sample measured were made from cellulose powder pressed into 4 cm diameter aluminium ring 0.4 t cm/sup -2/, and then 1 g of powdered sample (0.08 g cm/sup -2/) was placed on the disk and repressed at 1.6 t cm/sup -2/. X-ray measurements were performed for total XRF intensity (I/sub p/) at the characteristic line of each element and background intensity (I/sub b/) in vicinity of the line. The correction of matrix effect was achieved by X-ray intensity ratio of peak to background for each element. Eight standard rock samples from Geological Survey of Japan were used as standard materials, and linear calibration curves were obtained by the plot of I/sub p/ - I/sub b/ vs. concentration for Ca, Na and Pb and by the plot of I/sub p//I/sub b/ ratio vs. concentration for Si, Fe, Ti, K, ...
1987-03-01
XRF analysis of rock and sediment using standard rock samples
International Nuclear Information System (INIS)
A simple and rapid method is described for the determination of major and trace elements in rock and sediment samples by wavelength dispersive XRF. Sample measured were made from cellulose powder pressed into 4 cm diameter aluminium ring 0.4 t cm"-"2, and then 1 g of powdered sample (0.08 g cm"-"2) was placed on the disk and repressed at 1.6 t cm"-"2. X-ray measurements were performed for total XRF intensity (I_p) at the characteristic line of each element and background intensity (I_b) in vicinity of the line. The correction of matrix effect was achieved by X-ray intensity ratio of peak to background for each element. Eight standard rock samples from Geological Survey of Japan were used as standard materials, and linear calibration curves were obtained by the plot of I_p - I_b vs. concentration for Ca, Na and Pb and by the plot of I_p/I_b ratio vs. concentration for Si, Fe, Ti, K, P, Cl, Cr, Mn, Ni, Cu, Zn, Pb, Sr and Ba, ...
Energy Technology Data Exchange (ETDEWEB)
The high sensitivity of CaSO{sub 4}: Dy as a thermoluminescent material is a great advantage when dealing with low dose levels, as in diagnostic radiology procedures. However, these kinds of dosemeters present a high energy dependence that must be precisely determined in the energy range of interest. Dosimetric pellets of CaSO{sub 4}: Dy are produced at IPEN since the end of the 80 Th decade. These pellets are produced in three forms: conventional CaSO{sub 4}: Dy (50 mg); thin CaSO{sub 4}: Dy (20 mg) and CaSO{sub 4}: Dy + 10% C (20 mg). The main applications of these dosemeters are in personal and environmental dosimetry. In this study, CaSO{sub 4}: Dy pellets produced at IPEN were evaluated in diagnostic radiology standard beams. These qualities are based on the IEC 61267 standard, and they were established at an industrial X-ray system Pantak/Seifert, model ISOVOLT 160HS. Former studies evaluated CaSO{sub 4}: Dy of different origins in ...
2006-07-01
Energy Technology Data Exchange (ETDEWEB)
LEDF(Large Equipment Dismantling Facility) is the solid waste processing technology development facility that carries out high-volume reduction and low dosage processing. The high-volume reduction processing of the high dose {alpha}-waste configured with combustible waste, pvc and rubber, spent ion exchange resin, and noncombustible waste have been planned the incinerating and melting facility using the in-can type high frequency induction heating in LEDF. This test is intended to clarify the design data. It was confirmed that the incinerating and melting performance, molten solid properties and exhaust gas processing performance with pilot testing equipment and bench scale equipment. The result of this test are as follows. 1. Processing speed is 6.7 kg/h for the combustible waste, 13.0 kg/h for the ion exchange resin, and 30.0 kg/h for the noncombustible waste. For above optimum ...
1999-12-01
This Dissertation presents the author's investigation and development of a systematic method for evaluating the aerodynamic performance of Vertical Axis Wind Energy Capture Systems (WECS) apart from their electrical generation capability. The current standard method for specifying a wind energy machine is to discuss its rated power in kilowatts (or megawatts when capacity exceeds 100 kW). While this holistic method is effective for comparing machines it does not reveal the essential characteristics necessary for optimization of individual machine components. The method developed herein separates the performance characteristics of the WECS from the generation characteristics and isolates them for benchmarking and optimization. In order to develop an evaluation criterion, it was essential to evaluate and benchmark the current state of the art for wind energy capture. A thorough history of Vertical Axis Wind Turbine (VAWT) ...
2010-01-01
The effects of surface damage on RF cavity operation
Energy Technology Data Exchange (ETDEWEB)
We describe a model of damage in rf cavities and show how this damage can limit cavity operation. We first present a review of mechanisms that may or may not affect the ultimate fields that can be obtained in rf cavities, assuming that mechanical stress explains the triggers of rf breakdown events. We present a method of quantifying the surface damage caused by breakdown events in terms of the spectrum of field enhancement factors, Beta, for asperities on the surface. We then model an equilibrium that can develop between damage and conditioning effects, and show how this equilibrium can determine cavity performance and show experimental evidence for this mechanism. We define three functions that quantify damage, and explain how the parameters that determine this performance can be factored out and measured. We then show how this model can quantitatively explain the dependence of cavity performance on material, frequency, ...
2006-04-14
Materials considerations for the National Spallation Neutron Source target
Energy Technology Data Exchange (ETDEWEB)
The National Spallation Neutron Source (NSNS), in which neutrons are generated by bombarding a liquid mercury target with 1 GeV protons, will place extraordinary demands on materials performance. The target structural material will operate in an aggressive environment, subject to intense fluxes of high energy protons, neutrons, and other particles, while exposed to liquid mercury and to water. Components that require special consideration include the Hg liquid target container and protective shroud, beam windows, support structures, moderator containers, and beam tubes. In response to these demands a materials R and D program has been developed for the NSNS that includes: selection of materials; calculations of radiation damage; irradiations, post irradiation testing, and characterization; compatibility testing and characterization; design and implementation of a plan for monitoring of materials performance in service; and materials engineering ...
1997-08-01
FY 1987 current fiscal year work plan
Energy Technology Data Exchange (ETDEWEB)
This Current Year Work Plan presents a detailed description of the activities to be performed by the Joint Integration Office during FY87. It breaks down the activities into two major work areas: Program Management and Program Analysis. Program Management is performed by the JIO by providing technical planning and guidance for the development of advanced TRU waste management capabilities. This includes equipment/facility design, engineering, construction, and operations. These functions are integrated to allow transition from interim storage to final disposition. JIO tasks include program requirements identification, long-range technical planning, budget development, program planning document preparation, task guidance, task monitoring, information gathering and task reporting to DOE, interfacing with other agencies and DOE lead programs, integrating public involvement with program efforts, and preparation of program status ...
1986-12-01
Energy Technology Data Exchange (ETDEWEB)
The consistency of different instruments and methods for measuring two-dimensional (2D) power spectral density (PSD) distributions are investigated. The instruments are an interferometric microscope, an atomic force microscope (AFM) and the X-ray Reflectivity and Scattering experimental facility, all available at Lawrence Berkeley National Laboratory. The measurements were performed with a gold-coated mirror with a highly polished stainless steel substrate. It was shown that these three techniques provide essentially consistent results. For the stainless steel mirror, an envelope over all measured PSD distributions can be described with an inverse power-law PSD function. It is also shown that the measurements can be corrected for the specific spatial frequency dependent systematic errors of the instruments. The AFM and the X-ray scattering measurements were used to determine the modulation transfer function of the interferometric microscope. ...
2005-07-12
Energy Technology Data Exchange (ETDEWEB)
The consistency of different instruments and methods for measuring two-dimensional (2D) power spectral density (PSD) distributions are investigated. The instruments are an interferometric microscope, an atomic force microscope (AFM) and the X-ray Reflectivity and Scattering experimental facility, all available at Lawrence Berkeley National Laboratory. The measurements were performed with a gold-coated mirror with a highly polished stainless steel substrate. It was shown that these three techniques provide essentially consistent results. For the stainless steel mirror, an envelope over all measured PSD distributions can be described with an inverse power-law PSD function. It is also shown that the measurements can be corrected for the specific spatial frequency dependent systematic errors of the instruments. The AFM and the X-ray scattering measurements were used to determine the modulation transfer function of the interferometric microscope. ...
2005-04-17
Tests for the diagnosis of Clostridium difficile infection: the next generation.
Clostridium difficile (C. difficile) causes 25-30% of cases of antibiotic associated diarrhea and most cases of pseudomembranous colitis. Patients presenting with diarrhea after hospitalization for 3 or more days should be tested for C. difficile. There are many options available for testing, each of which has inherent advantages and disadvantages. Most laboratories perform toxin testing using an enzyme immunoassay method. In general these tests have sensitivities ranging from 60 to 70% and specificities of 98%. When using these methods, symptomatic patients with negative tests should be tested by another more sensitive method. Until recently, cell culture cytotoxicity neutralization assays (CCNAs) were considered the gold standard in the U.S. A two-step algorithm using an EIA for glutamate dehydrogenase detection followed by testing positives using CCNA, offered an improved alternative until the availability of molecular assays. Although early ...
2011-03-03
Review of UCN 3,4 PSA model based on ASME PRA standard rev.0
International Nuclear Information System (INIS)
Recently, under the de-regulation environment, nuclear industry has attempted various approaches to improve the economics of Nuclear Power Plants (NPP). One of these efforts is the Risk Informed/Performance-Based operation (RIPBO). This approach uses the risk and performance information to manage the resources effectively and efficiently that are used in the operation of NPP. In RIPBO, PSA quality is one of the most important things. The nuclear industry and regulatory body of U.S.A have developed a measure to evaluate the quality of PSA. NEI (Nuclear Energy Institute) has developed a guidance called 'NEI PRA Peer Review Guidance,' and NRC (Nuclear Regulatory Committee) and ASME have developed the 'PRA Standard.' In Korea, several projects are on going now, such as the extension of AOT/STI of RPS/ESFAS, Risk-Informed In-Service Inspection (RI-ISI). However, in Korea, there have been no attempts to evaluate the quality of ...
2011-03-13
Review of UCN 3,4 PSA model based on ASME PRA standard rev.0
Energy Technology Data Exchange (ETDEWEB)
Recently, under the de-regulation environment, nuclear industry has attempted various approaches to improve the economics of Nuclear Power Plants (NPP). One of these efforts is the Risk Informed/Performance-Based operation (RIPBO). This approach uses the risk and performance information to manage the resources effectively and efficiently that are used in the operation of NPP. In RIPBO, PSA quality is one of the most important things. The nuclear industry and regulatory body of U.S.A have developed a measure to evaluate the quality of PSA. NEI (Nuclear Energy Institute) has developed a guidance called 'NEI PRA Peer Review Guidance,' and NRC (Nuclear Regulatory Committee) and ASME have developed the 'PRA Standard.' In Korea, several projects are on going now, such as the extension of AOT/STI of RPS/ESFAS, Risk-Informed In-Service Inspection (RI-ISI). However, in Korea, there have been no ...
2003-05-01
Review of KSNP LPSD PSA model based of ANS LPSD PRA standard, rev.0
Energy Technology Data Exchange (ETDEWEB)
Recently, under the de-regulation environment, nuclear industry has attempted various approaches to improve the economics of Nuclear Power Plants (NPP). One of these efforts is the Risk Informed/Performance-based Operation (RIPBO). This approach uses the risk and performance information to manage the resources effectively and efficiently that are used in the operation of NPP. In RIPBO, PSA quality is one of the most important things. The nuclear industry and regulatory body of U.S.A have developed a measure to evaluate the quality of PSA. NEI (Nuclear Energy Institute) has developed a guidance called 'NEI PRA Peer Review Guidance,' and NRC (Nuclear Regulatory Committee) and ASME have developed the 'PRA Standard.' In Korea, several projects are on going now, such as the extension of AOT/STI of RPS/ESFAS, Risk-informed In-service Inspection (RI-ISI). However, in Korea, there have been no ...
2004-02-01
Pipeline risk assessment and risk management
Energy Technology Data Exchange (ETDEWEB)
The objective of this work group was to identify obstacles to the development of better risk management practices and performance standards in the pipeline industry. An outline of developments in pipeline risk assesment management was presented, including an update of the Risk Based Design and Assessment annex and other CSA Z662 code developments. It was suggested that progress in risk management require that acceptable levels of risk and reliability need to be defined. Environmental and safety consequence analysis was recommended, as well as failure frequency estimation and assessment of distribution systems. Guidelines for Integrity Management Programs (IMPs) were reviewed. It was noted that CSA Z662 will become mandatory for sour gas in 2005 and may become mandatory for all onshore pipelines in 2007. Operating company procedures in relation to hazards with significant consequences were discussed. It was noted that companies should assess ...
2005-07-01
Energy Technology Data Exchange (ETDEWEB)
Our objective was to evaluate the feasibility of ultra-low-dose scanning for multislice CT colonography in the detection of colorectal lesions. Twenty-seven patients (14 men, 13 women) with clinical indication for conventional colonoscopy were recruited. Multislice spiral CT (Somatom Plus 4 Volume Zoom, Siemens, Germany) examinations were performed after standard oral colonoscopic preparation and colonic distension with room air. Images were acquired using 2.5-mm collimation, 3.0-mm slice thickness, standard reconstruction kernel, 140 kVp, and 10 mAs. Supine and prone acquisitions were obtained in all patients. Images were analyzed on a workstation by two gastrointestinal radiologists. Conventional colonoscopy was performed on the same day in all patients and represented the standard of reference. Total radiation exposure was also calculated. All colorectal cancers were correctly ...
2003-06-01
Discrepancies in molar extinction coefficients of Fe"3"+ in Fricke dosimetry
International Nuclear Information System (INIS)
Values of the chemical yield, G, and of the molar extinction coefficient, epsilon, for Fricke dosimetry, have been recommended by ICRU. For epsilon, the value in ICRU Reports 17 and 21, 2205 1.mol"-"1.cm"-"1, based on an analysis of 83 reported values. It was suggested that, where neither a careful wavelength calibration nor absorbance linearity checks had been performed, a standard error of 1.5% should be assumed; otherwise 0.15% could be accepted. Alternatively, the accuracy in applying this chemical dose meter was considered improved if there was an independent determination of epsilon with the same spectrophotometer as was used for the determination of the optical density of irradiated Fricke solution. The accuracy claimed for both methods remains questionable, since no complete argumentation could be given for the differences of up to 13% in the published values. Taking into account the discussion of the sources of error by Bryant, ...
1977-12-09
Standardization of rules for manufacturing normal electrical equipment for mining
Energy Technology Data Exchange (ETDEWEB)
Information is provided about standardization and unification of rules for manufacturing normal electrical equipment designed for operating in underground shafts when there is no danger of explosion of gas, dust or steam. An analysis is made of the requirements included in the CEMA standard and in the state standard.
1983-01-01
Energy Technology Data Exchange (ETDEWEB)
The effective fraction of delayed photoneutrons ({beta}{sup ph}) has been theoretically defined and experimentally determined in various different configurations of the LWR-PROTEUS critical facility. The peculiarity lies in the fact that the reactor has D{sub 2}O in only one of the four fuelled zones, thus D({gamma},n)H reactions take place mainly in this region. The work is divided into three parts. The first part is devoted to the description of the LWR-PROTEUS facility and to the measurements of {beta}{sup ph}. These experimental values are derived from standard inverse-kinetics analysis of neutron flux decay experiments for each of seven different configurations, with nine additional groups of neutron precursors to account for photoneutron effects. In the second part, the coupled neutron and gamma Boltzmann equations are reduced to exact point kinetics equations using the photon infinite-velocity approximation, and then ...
2003-11-01
Gas fired heaters and ventilation system improve indoor air quality and thermal comfort
Energy Technology Data Exchange (ETDEWEB)
Rotex Inc. has designed and manufactured industrial sifting equipment since 1844. This site (an existing industrial facility) encompasses approximately 140,000 ft[sup 2] (13,006 m[sup 2]) of offices, R D shops, assembly and storage areas, as well as a large welding shop that was the main focus of this project. This facility consists of three separate buildings that are all connected and open to one another. The original building dates from 1908. The newest addition (32,400 ft[sup 2]; 3,010 m[sup 2]) was added in 1977, and is referred to as the 77 Building. This building was initially equipped with oil fired heating equipment due to the moratorium on new gas sales that was in effect at that time. This project was driven by the client's need to remove underground oil storage tanks to comply with environmental standards. This article describes the 77 Building conversion from oil to an environmentally cleaner fuel, ...
1994-03-01
Energy Technology Data Exchange (ETDEWEB)
The feasibility study was conducted on a model project in Vietnam, aimed at solving the environmental pollution problems resulting from use of coal by demonstrating and disseminating the Japan's environmental technologies in the Southeast Asian countries. The feasibility study was conducted for the Cua Ong Coal Preparation Enterprise, which has the largest coal preparation capacity in Vietnam and port facilities. It is treating raw coal from 10 coal mines for classification and preparation, and shipping coal of various types that meet the standards for domestic use and export. The survey results point out that unrecovered coal remains in waste water discharged from the coal preparation plants to pollute the sea area, and that quantity of the refuse increases because of the unrecovered coal it contains. The environmental technologies needed to introduce include modification to variable wave pattern type jigging separator, refuse height ...
2001-06-01
Radionuclide air emissions report for the Hanford Site -- calendar year 1997
Energy Technology Data Exchange (ETDEWEB)
This report documents radionuclide air emission from the Hanford Site in 1997, and the resulting effective dose equivalent to the maximally exposed member of the public, referred to as the MEI. The report has been prepared in accordance with reporting requirements in the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, National Emissions Standards for Hazardous Air Pollutants, Subpart H, National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities. This report has also been prepared in accordance with the reporting requirements of the Washington Administrative Code Chapter 246-247, Radiation Protection-Air Emissions. The effective dose equivalent to the MEI from the Hanford Site`s 1997 point source emissions was 1.2 E-03 mrem (1.2 E-05 mSv), which is well below the 40 CFR 61 Subpart H regulatory limit of 10 mrem/yr. Radon and thoron emissions, ...
1998-06-17
International Nuclear Information System (INIS)
One of the initial stages in ecological risk assessment for hazardous waste sites is the screening of contaminants to determine which of them are worthy of further consideration as ''contaminants of potential concern.'' This process is termed ''contaminant screening.'' It is performed by comparing measured ambient concentrations of chemicals to benchmark concentrations. Currently, no standard benchmark concentrations exist for assessing contaminants in soil with respect to their toxicity to plants. This report presents a standard method for deriving benchmarks for this purpose (phytotoxicity benchmarks), a set of data concerning effects of chemicals in soil or soil solution on plants, and a set of phytotoxicity benchmarks for 34 chemicals potentially associated with US Department of Energy (DOE) sites. Chemicals that are found in soil at concentrations exceeding both the phytotoxicity benchmark and the background ...
International Nuclear Information System (INIS)
One of the initial stages in ecological risk assessments for hazardous waste sites is the screening of contaminants to determine which of them are worthy of further consideration as open-quotes contaminants of potential concern.close quotes This process is termed open-quotes contaminant screening.close quotes It is performed by comparing measured ambient concentrations of chemicals to benchmark concentrations. Currently, no standard benchmark concentrations exist for assessing contaminants in soil with respect to their toxicity to soil- and litter-dwelling invertebrates, including earthworms, other micro- and macroinvertebrates, or heterotrophic bacteria and fungi. This report presents a standard method for deriving benchmarks for this purpose, sets of data concerning effects of chemicals in soil on invertebrates and soil microbial processes, and benchmarks for chemicals potentially associated with United States Department ...
Energy Technology Data Exchange (ETDEWEB)
This paper presents the history and objectives of the development of a standard method for the measurement of organic contaminants in biomass producer gases. Recently, a project with that title has started in the European 5{sup th} Framework Programme. The structure of this project with acronym 'Tar Protocol' is also described in this paper. The project is performed by 17 partners and continues earlier work initiated by IEA (International Energy Agency), DoE (Department of Energy) and EU (European Union) in 1998. The project aims to combine two draft Protocols that resulted from this earlier work. The Tar Protocol will be developed for accurate measurement of organic contaminants ('tars') over a large range of concentrations (1 mg/Nm{sup 3} to 100 g/Nm{sup 3}) and conditions (0 - 900 deg C; 0.9 - 60 bars). Besides, a particulate concentration will be determined too. Together with the Protocol comes a number ...
2000-06-01
Support vector machines for nuclear reactor state estimation
Energy Technology Data Exchange (ETDEWEB)
Validation of nuclear power reactor signals is often performed by comparing signal prototypes with the actual reactor signals. The signal prototypes are often computed based on empirical data. The implementation of an estimation algorithm which can make predictions on limited data is an important issue. A new machine learning algorithm called support vector machines (SVMS) recently developed by Vladimir Vapnik and his coworkers enables a high level of generalization with finite high-dimensional data. The improved generalization in comparison with standard methods like neural networks is due mainly to the following characteristics of the method. The input data space is transformed into a high-dimensional feature space using a kernel function, and the learning problem is formulated as a convex quadratic programming problem with a unique solution. In this paper the authors have applied the SVM method for data-based state estimation in nuclear ...
2000-02-14
Reducing indoor air formaldehyde concentrations
Energy Technology Data Exchange (ETDEWEB)
Urea-formaldehyde resin bonded particle board, medium density fiberboard and plywood paneling are used as flooring, wall paneling, for cabinet work and in furniture, and are present in almost every office, home and public building. If large quantities of these products are used in poorly ventilated spaces, high manufacturing quality control is necessary to avoid problems of latent formaldehyde release. Indoor air formaldehyde concentrations depend on the nature of the product, the product surface to air volume (loading) factor, temperature, humidity, age and product emission rates. Standard test methods are now available for measuring product emission rates that make it possible to predict the performance of UF-bonded pressed wood materials if use conditions and environmental parameters are known. Recent modifications in adhesive and board manufacturing parameters have made it possible to reduce formaldehyde emission significantly, and ...
1985-08-01
Energy Technology Data Exchange (ETDEWEB)
Purpose: calculation of conversion coefficients for the reconstruction of organ doses from entrance doses for abdomen radiographs of 0, 1, 5, 10, 15, and 30-year-old patients in conventional pediatric radiology for the radiographic settings recommended by the German and European guidelines for quality management in diagnostic radiology. Materials und method: using the commercially available personal computer program PCXMC developed by the Finnish Center for Radiation and Nuclear Safety (Saeteilyturvakeskus STUK), conversion coefficients for conventional abdomen radiographs were calculated performing Monte Carlo simulations in mathematical hermaphrodite phantom models describing patients of different ages. The possible clinical variation of beam collimation was taken into consideration by defining optimal and suboptimal radiation fields on the phantoms' surfaces. Results: conversion coefficients for the reconstruction of organ does in about 40 organs and ...
2009-10-15
Measurement of the /SUP 242m/ Am neutron fission cross section
Energy Technology Data Exchange (ETDEWEB)
The fission cross section of /SUP 242m/ Am has been measured from 0.005 eV to 20 MeV using time-of-flight techniques at the Oak Ridge Electron Linear Accelerator. A hemispherical plate fission ionization chamber with five pairs of plates contained three deposits totaling 507 ..mu..g of /SUP 242m/ Am, one deposit of 168 ..mu..g /sup 235/U, and a ''weightless'' deposit of /sup 252/Cf, which served as a monitor of chamber performance. The fission of /sup 235/U, served as the cross-section standard for energies above 101 keV while /sup 6/Li(n,..cap alpha..), normalized to /sup 235/U fission in the 7.8- to 11.0-eV interval, served as a shape standard below 101 keV. Approximately 360 h of data were obtained at a flight path distance of 9.1 m, primarily with 40-ns bursts. Particular attention was paid to correction of backgrounds, especially inscattered-neutron-induced events. The fission ...
1983-05-01
Measurement of the /SUP 242m/ Am neutron fission cross section
International Nuclear Information System (INIS)
The fission cross section of /SUP 242m/ Am has been measured from 0.005 eV to 20 MeV using time-of-flight techniques at the Oak Ridge Electron Linear Accelerator. A hemispherical plate fission ionization chamber with five pairs of plates contained three deposits totaling 507 #mu#g of /SUP 242m/ Am, one deposit of 168 #mu#g "2"3"5U, and a ''weightless'' deposit of "2"5"2Cf, which served as a monitor of chamber performance. The fission of "2"3"5U, served as the cross-section standard for energies above 101 keV while "6Li(n,#alpha#), normalized to "2"3"5U fission in the 7.8- to 11.0-eV interval, served as a shape standard below 101 keV. Approximately 360 h of data were obtained at a flight path distance of 9.1 m, primarily with 40-ns bursts. Particular attention was paid to correction of backgrounds, especially inscattered-neutron-induced events. The fission resonance integral was found to be 1800 + or - 65 b.
MODFLOW 2.0: A program for predicting moderator flow patterns
Energy Technology Data Exchange (ETDEWEB)
Sudden changes in the temperature of flowing liquids can result in transient buoyancy forces which strongly impact the flow hydrodynamics via flow stratification. These effects have been studied for the case of potential flow of stratified liquids to line sinks, but not for moderator flow in SRS reactors. Standard codes, such as TRAC and COMMIX, do not have the capability to capture the stratification effect, due to strong numerical diffusion which smears away the hot/cold fluid interface. A related problem with standard codes is the inability to track plumes injected into the liquid flow, again due to numerical diffusion. The combined effects of buoyant stratification and plume dispersion have been identified as being important in operation the Supplementary Safety System which injects neutron-poison ink into SRS reactors to provide safe shutdown in the event of safety rod failure. The MODFLOW code discussed here provides transient moderator ...
1991-07-01
MODFLOW 2. 0: A program for predicting moderator flow patterns
Energy Technology Data Exchange (ETDEWEB)
Sudden changes in the temperature of flowing liquids can result in transient buoyancy forces which strongly impact the flow hydrodynamics via flow stratification. These effects have been studied for the case of potential flow of stratified liquids to line sinks, but not for moderator flow in SRS reactors. Standard codes, such as TRAC and COMMIX, do not have the capability to capture the stratification effect, due to strong numerical diffusion which smears away the hot/cold fluid interface. A related problem with standard codes is the inability to track plumes injected into the liquid flow, again due to numerical diffusion. The combined effects of buoyant stratification and plume dispersion have been identified as being important in operation the Supplementary Safety System which injects neutron-poison ink into SRS reactors to provide safe shutdown in the event of safety rod failure. The MODFLOW code discussed here provides transient moderator ...
1991-07-01
Improved H{infinity} power system stabilizer
Energy Technology Data Exchange (ETDEWEB)
In designing power system stabilizer (PSS), a major difficulty is to successfully treat the system`s uncertainties. These uncertainties arise because of changes in operating conditions, approximations in modeling, parameter variations caused by faults, etc. It is known that in the presence of uncertainties, conventional methodologies such as linear optimal technique, adaptive controls, etc., may fail to guarantee the stability of the system. On the other hand, the H{infinity} control theory provides potential ability to overcome this problem. However, some limitations still exist in the treatment of uncertainty. That is, the existing standard H{infinity}-PSSs cannot adequately treat the system uncertainties. Moreover, performance problems can arise in this approach due to the pole-zero cancellation phenomenon. To deal with the above mentioned limitations, a new design methodology for H{infinity}-PSS based on the `numerator-denominator` ...
1996-11-20
Evaluation of light-water-moderated, mixed-oxide, hexagonal pitch lattices
International Nuclear Information System (INIS)
The use of previously measured mixed-oxide (MOX) fuel systems as benchmarks can be valuable tool in computational analysis and quality assurance efforts. The Fissile Materials Disposition Program (FMDP) has identified these experiments as potential benchmarks, or standards, for VVER's employing MOX fuel. Standards for the analysis of these benchmark experiments were based on those used in the recent compilation International Handbook of Evaluated Criticality Safety Benchmark Experiments begun in 1992 by the U.S. Department of Energy. The Los Alamos National Laboratory's archives were explored for log-book records of these experiments without success. These experiments were the first to use MOX fuel in light water. Three approach-to-critical experiments were performed using fuel rods at various pitches and different plutonium-oxide concentrations. A parallel program verified the prediction of critical condition as similar ...
1997-11-16
Design of a welltest for determining two-phase hydraulic properties
Energy Technology Data Exchange (ETDEWEB)
This report describes the design of a well test to determine two-phase hydraulic properties of a low permeability, low porosity formation. Estimation of gas-related parameters in such formations is difficult using standard pumping tests mainly because of the strong fluctuations in the pressure and flow rate data which are a consequence of gas bubbles evolving in the test interval. Even more important is the fact that the data do not allow distinguishing among alternative conceptual models. The estimated parameters are therefore uncertain, highly correlated, and ambiguous. In this study we examine a test sequence that could be appended to a standard hydraulic testing program. It is shown that performing a series of water and gas injection tests significantly reduces parameter correlations, thus decreasing the estimation error. Moreover, the extended test sequence makes possible the identification of the model that describes ...
1995-01-01
Collection efficiency and decontamination factor of HEPA filter
International Nuclear Information System (INIS)
It is very important in a nuclear air cleaning system that HEPA (High Efficiency Particulate Air) filter is for reduction of releasing amounts of airborne radioactive particles. HEPA filter, by definition, has a minimum collection efficiency of 99.97 % for 0.3 #mu#m particles. However, DF (Decontamination Factor), which is necessary for safety management, can not be directly derived from the efficiency. And the current standard defined for 0.3 #mu#m particles has no scientific justification, because it has been found that the most penetrating particle size through HEPA filter is not always 0.3 #mu#m. In the present paper, a numerical experiment was made in order to estimate a relationship between DF and the efficiency. And new standard, in which the minimum DF is able to be easily obtained, was proposed. In the multistage filtration system, it was found that lower values of DF was possible to be experimentally indicated in the second and the ...
Alloy 800: New stress rupture and creep data for pressurized components in high temperature reactors
Energy Technology Data Exchange (ETDEWEB)
In an HTR plant high temperature components of Alloy 800 materials are subjected to temperatures from about 550 to 850degC in the long term; higher temperatures may occur in the short term. Thus the creep and stress-rupture parameters govern the design of these components. Since in recent years the scope of experimental data available for Alloy 800 materials has considerably increased, a new evaluation of the creep and creep-rupture properties was performed using a data bank computer. The relationships between the characteristics of the creep and creep-rupture behaviour and the metallurgical parameters were investigated by multilinear regression analyses. On the basis of the results of these analyses and after discussion in material expert committees new material specifications were determined for different types of Alloy 800. They were included into the draft standards DIN 17459 and DIN 17460 under the material standard ...
1990-05-01
Alloy 800: New stress rupture and creep data for pressurized components in high temperature reactors
International Nuclear Information System (INIS)
In an HTR plant high temperature components of Alloy 800 materials are subjected to temperatures from about 550 to 850degC in the long term; higher temperatures may occur in the short term. Thus the creep and stress-rupture parameters govern the design of these components. Since in recent years the scope of experimental data available for Alloy 800 materials has considerably increased, a new evaluation of the creep and creep-rupture properties was performed using a data bank computer. The relationships between the characteristics of the creep and creep-rupture behaviour and the metallurgical parameters were investigated by multilinear regression analyses. On the basis of the results of these analyses and after discussion in material expert committees new material specifications were determined for different types of Alloy 800. They were included into the draft standards DIN 17459 and DIN 17460 under the material standard ...
A structured approach to the assessment of the quality culture in nuclear installation
International Nuclear Information System (INIS)
INSAG has emphasized that safety culture has two general components: the organizational framework and the attitude of the staff. To develop a structured approach to the assessment of safety culture, we propose that the highly formalized nature of nuclear power plant organizations be exploited. The prime coordinating mechanism of NPP organizations is the standardization of work processes, where a work process is defined as a standardized sequence of tasks designed to achieve a specific goal (an example is the maintenance work process). The predictable nature of work processes is exploited by the Work Process Analysis Model (WPAM) to conduct a systematic analysis that identifies the desirable characteristics of work processes and develops performance measures for their strengths and weaknesses. These can provide a set of tangible characteristics of a good safety culture. It is argued in this paper that the analysis of normal ...
1995-04-01
Energy Technology Data Exchange (ETDEWEB)
The Subcommittee for Surveillance of Nuclear Medicine Practice has implemented a survey for actual nuclear medicine practice in Japan every 5 years. This article reports on the third survey implemented during a one-month period in June 1992. Questionnaires were sent to all 1256 facilities employing radiopharmaceuticals in routine practice, and 1162 (92.5%) answered. In vivo nuclear medicine examinations per day were performed in 6600 cases. SPECT accounted for 19.4%, as compared with 7.1% in the 1987 survey. According to organs, the frequency of examination for the cerebrospinal region was 3.2 and 2.2 times higher than that in the 1982 and 1987 surveys, respectively, whereas for the thyroid gland it was 0.6-fold and 0.7-fold that of these surveys. The proportion of bone scintigraphy was the highest (24.5%), followed by tumor scintigraphy (14.1%) and myocardial scintigraphy (11.9%). The frequency of myocardial and cerebral blood flow ...
1993-09-01
Preliminary test conditions for KNGR SBLOCA DVI ECCS performance test
Energy Technology Data Exchange (ETDEWEB)
The Korean Next Generation Reactor (KNGR) adopts 4-train Direct Vessel Injection (DVI) configuration and injects the safety injection water directly into the downcomer through the 8.5'' DVI nozzle. Thus, the thermal hydraulic phenomena such as ECCS mixing and bypass are expected to be different from those observed in the cold leg injection. In order to investigate the realistic injection phenomena and modify the analysis code developed in the basis of cold leg injection, thermal hydraulic test with the performance evaluation is required. Preliminarily, the sequence of events and major thermal hydraulic phenomena during the small break LOCA for KNGR are identified from the analysis results calculated by the CEFLASH-4AS/REM. It is shown from the analysis results that the major transient behaviors including the core mixture level are largely affected by the downcomer modeling. Therefore, to investigate the proper thermal hydraulic phenomena occurring ...
1999-03-01
International Nuclear Information System (INIS)
Full text of publication follows: As the coolant experiences no phase change in the core, SCWRs, unlike LWRs, cannot use design criteria based on the critical heat flux concept. The commonly accepted practice in SCWRs is to specify cladding temperature limits that must be met during transient and accident events. Therefore for the design of the SCWR, it is very important to predict the heat transfer coefficient to the supercritical water coolant with great accuracy. Our recent study focuses on the critical issue of measuring heat transfer to supercritical water at prototypical SCWR conditions and to develop the tools to predict the SCWR thermal behavior. A heat transfer test loop using a surrogate fluids, CO_2, is under construction. The reason of using CO_2 instead of water is that (i) valuable insight of the physical phenomena can be obtained with this fluid, and (ii) some existing facilities already used surrogate fluids, which in general have lower critical ...
2005-10-02
The Performance of Spent Fuel Casks in Severe Tunnel Fires
International Nuclear Information System (INIS)
The Nuclear Regulatory Commission (NRC), working with the National Institute of Standards and Technology (NIST), Pacific Northwest National Laboratory (PNNL), and the National Transportation Safety Board (NTSB), performed analyses to predict the response of various spent fuel transportation cask designs when exposed to a fire similar to that which occurred in the Howard Street railroad tunnel in downtown Baltimore, Maryland on July 18, 2001. The thermal performance of three different spent fuel cask designs (HOLTEC HI-STAR 100, TransNuclear TN-68, and NAC-LWT) was evaluated with the ANSYSR and COBRA-SFS analysis codes, utilizing boundary conditions for the tunnel fire obtained using NIST's Fire Dynamics Simulator (FDS) code. NRC Staff evaluated the potential for a release of radioactive material from each of the three transportation casks analyzed for the Baltimore tunnel fire scenario. The results of these analyses are ...
2005-11-01
Manufacturing of small scale W monoblock mockups by hot radial pressing
International Nuclear Information System (INIS)
In the frame of the European Technology R and D programme for International thermonuclear experimental reactor (ITER) and in the area of high heat flux plasma facing components (HHFC), representative small-scale mock-ups were manufactured and tested to compare different concepts and joining technologies (i.e. active brazing, hot isostatic pressing (HIPping), diffusion bonding, etc.). On the basis of the results obtained by thermal fatigue tests, the monoblock concept resulted to be the most robust one, particularly when the HIPping manufacturing technology is used. Within this programme, ENEA developed an alternative technique for manufacturing plasma-facing components with a monoblock geometry of the ITER machine. The basic idea of this technique, named hot radial pressing (HRP), is to perform a radial diffusion bonding between the cooling tube and the armour tile by pressurising the internal tube only and by keeping the process parameters within the range in ...
2003-09-01
Fiscal year 1996 U.S. Department of Energy, Richland Operations Office Site summary baseline
International Nuclear Information System (INIS)
The technical baseline is a hierarchical description of the Hanford Site cleanup mission. This technical baseline does not address the science, technology, or economic transition missions. It begins with a definition of the existing conditions at the Hanford Site, provides a description of the end product or mission accomplishments at completion, presents a statement of the major requirements and constraints that must be observed during the performance of the mission, and provides a statement of the top-level strategic approach to accomplish the mission. Mission-level interfaces are also described. This information is further defined hierarchically in increasing levels of detail. This definition is composed of the following major elements: functions that are key task descriptions; requirements that are the measurable standards to which the functions must be performed; architectures which are specific engineering solutions ...
2009-06-01
Application of hydraulic network analysis to motor operated butterfly valves in nuclear power plants
International Nuclear Information System (INIS)
This paper presents the application of hydraulic network analysis to evaluate the performance of butterfly valves in nuclear power plant applications. Required actuation torque for butterfly valves in high-flow applications is often dictated by peak dynamic torque. The peak dynamic torque, which occurs at some intermediate disc position, requires accurate evaluation of valve flow rate and pressure drop throughout the valve stroke. Valve flow rate and pressure drop are significantly affected by the valve flow characteristics and the hydraulic system characteristics, such as pumping capability, piping resistances, single and parallel flow paths, system hydrostatic pressure, and the location of the motor-operated valve (MOV) within the system. A hydraulic network analysis methodology that addresses the effect of these parameters on the MOV performance is presented. The methodology is based on well-established engineering principles. The ...
1992-07-01
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