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in subjects: "210100 -- Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled"  
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Nuclear power in the Soviet Bloc

Description: The growth of Soviet Bloc nuclear power generation to the end of the century is evaluated on the basis of policy statements of objectives, past and current nuclear power plant construction, and trends in the potential for future construction. Central to this study is a detailed examination of individual reactor construction and site development that provides specific performance data not given elsewhere. A major commitment to nuclear power is abundantly clear and an expansion of ten times in nu… more
Date: March 1, 1982
Creator: Davey, W.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Implementation and application of RCP system at BNL

Description: The implementation of the RCPO1 Monte Carlo system at the Brookhaven National Laboratory Central Scientific Computing Facility is discussed. Initial benchmarking experience and an LWR core physics application will be described.
Date: January 1, 1982
Creator: Eisenhart, L.D. & Todosow, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Compare containment subcompartment analysis code evaluation. [PWR; BWR]

Description: Nuclear power plant subcompartment analyses are required to determine the containment pressure distribution that might result from a loss-of-coolant accident. The pressure distribution is used to calculate structural and mechanical design loads. The COMPARE code is used widely to perform subcompartment analysis. However, several simplifying assumptions are utilized to facilitate solution of the complex transient, two-phase, multidimensional flow problem. In particular, it is assumed that the fl… more
Date: January 1, 1982
Creator: Gido, R.G. & Koestel, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Implementation and application of RCP system at BNL

Description: The implementation of the RCP01 Monte Carlo system at the Brookhaven National Laboratory Central Scientific Computing Facility is described. Newly written system independent software is stressed. Finally, initial benchmarking experience and an LWR core physics application are described.
Date: January 1, 1982
Creator: Eisenhart, L.D. & Todosow, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Technical evaluation report on the monitoring of electric power to the reactor-protection system for the Pilgrim Nuclear Power Station

Description: This report documents the technical evaluation of the monitoring of electric power to the reactor protection system (RPS) at the Pilgrim Nuclear Power Station. The evaluation is to determine if the proposed design modification will protect the RPS from abnormal voltage and frequency conditions which could be supplied from the power supplies and will meet certain requirements set forth by the Nuclear Regulatory Commission. The proposed design modifications will protect the RPS from sustained abn… more
Date: April 29, 1982
Creator: Selan, J.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Use of separate-effects experiments in verification of system thermal-hydraulics

Description: In recent years, a number of advanced, best-estimate systems codes such as TRAC and RELAP5 have been developed in order to accurately predict the consequences of various postulated accidents and transients in Light Water Reactor (LWR) systems. Although these codes had to go through some verification or assessment during the developmental stage, it has been recognized that an independent assessment of these codes is necessary before they should be applied to any decision making process. The USNR… more
Date: January 1, 1982
Creator: Saha, P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Boundary effects on Zircaloy-4 cladding deformation in LOCA simulation tests. [PWR; BWR]

Description: Deformation behavior of Zircaloy-4 cladding under simulated loss-of-coolant accident (LOCA) conditions is being investigated in the Multirod Burst Test (MRBT) program in single rod and multirod tests. In these tests, internally-pressurized unirradiated Zircaloy-4 tubes containing internal electrical heaters are heated to failure in a low-pressure, superheated-steam environment (200 < Re < 800). The results provide a data base for evaluating deformation and blockage models employed with design-b… more
Date: January 1, 1982
Creator: Longest, A.W.; Chapman, R.H. & Crowley, J.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Summary and bibliography of safety-related events at boiling-water nuclear power plants as reported in 1980

Description: This document presents a bibliography that contains 100-word abstracts of event reports submitted to the US Nuclear Regulatory Commission concerning operational events that occurred at boiling-water-reactor nuclear power plants in 1980. The 1547 abstracts included on microfiche in this bibliography describe incidents, failures, and design or construction deficiencies that were experienced at the facilities. These abstracts are arranged alphabetically by reactor name and then chronologically for… more
Date: March 1, 1982
Creator: McCormack, K.E. & Gallaher, R.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Approach to Numerical Safety Guidelines Based on a Core Melt Criterion. [PWR; BWR]

Description: A plausible approach is proposed for translating a single level criterion to a set of numerical guidelines. The criterion for core melt probability is used to set numerical guidelines for various core melt sequences, systems and component unavailabilities. These guidelines can be used as a means for making decisions regarding the necessity for replacing a component or improving part of a safety system. This approach is applied to estimate a set of numerical guidelines for various sequences of c… more
Date: January 1, 1982
Creator: Azarm, M. A. & Hall, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of subcooling and rod drop speed on the BWR rod drop accident

Description: The techniques and models used in the analysis of the control rod drop accident (CRDA) in a BWR have ranged from approximate conservative methods with a simple feedback model to detailed representations of the thermal-hydraulic and neutronic mechanisms. In a recent paper Cheng and Diamond presented a detailed evaluation of the CRDA and the effects of varying a number of important accident parameters. Their calculations performed with the BNL-TWIGL core dynamics code, have shown that the effect … more
Date: January 1, 1982
Creator: Cokinos, D.; Carew, J. & Aronson, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Effect of bundle size on cladding deformation in LOCA simulation tests. [PWR; BWR]

Description: Two LOCA simulation tests were conducted to investigate the effects of temperature uniformity and radial restraint boundary conditions on Zircaloy cladding deformation. In one of the tests (B-5), boundary conditions typical of a large array were imposed on an inner 4 x 4 square array by two concentric rings of interacting guard fuel pin simulators. In the other test (B-3), the boundary conditions were imposed on a 4 x 4 square array by a non-interacting heated shroud. Test parameters conducive … more
Date: January 1, 1982
Creator: Chapman, R.H.; Crowley, J.L. & Longest, A.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Light-water-reactor coupled neutronic and thermal-hydraulic codes

Description: An overview is presented of computer codes that model light water reactor cores with coupled neutronics and thermal-hydraulics. This includes codes for transient analysis and codes for steady state analysis which include fuel depletion and fission product buildup. Applications in nuclear design, reactor operations and safety analysis are given and the major codes in use in the USA are identified. The neutronic and thermal-hydraulic methodologies and other code features are outlined for three st… more
Date: January 1, 1982
Creator: Diamond, D. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analysis of a partial scram event in a typical BWR/4

Description: A study has been made of core thermal-hydraulic conditions and containment suppression pool water temperature following a partial failure to scram in a BWR 4. This was motivated by the occurrence of such an incident in the Browns Ferry Unit 3. If suppression pool temperature should rise too much, the effectiveness of the suppression pool can be impaired. However, the pool temperature in the present case rose no more than 58 degrees (F), which is considered to be acceptable. In this study the tr… more
Date: January 1, 1982
Creator: Lu, M. S.; Shier, W.; Levine, M. M. & Cerbone, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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BWR containment failure analysis during degraded-core accidents

Description: This paper presents a containment failure mode analysis during a spectrum of postulated degraded core accident sequences in a typical 1000-MW(e) boiling water reactor (BWR) with a Mark-I wetwell containment. Overtemperature failure of containment electric penetration assemblies (CEPAs) has been found to be the major failure mode during such accidents.
Date: June 6, 1982
Creator: Yue, D.D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Critical heat-flux experiments under low-flow conditions in a vertical annulus. [PWR; BWR; LMFBR]

Description: An experimental study was performed on critical heat flux (CHF) at low flow conditions for low pressure steam-water upward flow in an annulus. The test section was transparent, therefore, visual observations of dryout as well as various instrumentations were made. The data indicated that a premature CHF occurred due to flow regime transition from churn-turbulent to annular flow. It is shown that the critical heat flux observed in the experiment is essentially similar to a flooding-limited burno… more
Date: March 1, 1982
Creator: Mishima, K. & Ishii, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor safety research programs. Quarterly report, January-March 1982

Description: This document summarizes work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1982, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzin… more
Date: July 1, 1982
Creator: Edler, S.K. (ed.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Chemical aspects of pellet-cladding interaction in light water reactor fuel elements

Description: In contrast to the extensive literature on the mechanical aspects of pellet-cladding interaction (PCI) in light water reactor fuel elements, the chemical features of this phenomenon are so poorly understood that there is still disagreement concerning the chemical agent responsible. Since the earliest work by Rosenbaum, Davies and Pon, laboratory and in-reactor experiments designed to elucidate the mechanism of PCI fuel rod failures have concentrated almost exclusively on iodine. The assumption … more
Date: January 1, 1982
Creator: Olander, D.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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ANS shielding standards for light-water reactors

Description: The purpose of the American Nuclear Society Standards Subcommittee, ANS-6, Radiation Protection and Shielding, is to develop standards for radiation protection and shield design, to provide shielding information to other standards-writing groups, and to develop standard reference shielding data and test problems. A total of seven published ANS-6 standards are now current. Additional projects of the subcommittee, now composed of nine working groups, include: standard reference data for multigrou… more
Date: January 1, 1982
Creator: Trubey, D. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Comparison of the radiological impacts of thorium and uranium nuclear fuel cycles

Description: This report compares the radiological impacts of a fuel cycle in which only uranium is recycled, as presented in the Final Generic Environmental Statement on the Use of Recycle Plutonium in Mixed Oxide Fuel in Light Water Cooled Reactors (GESMO), with those of the light-water breeder reactor (LWBR) thorium/uranium fuel cycle in the Final Environmental Statement, Light Water Breeder Reactor Program. The significant offsite radiological impacts from routine operation of the fuel cycles result fro… more
Date: March 1, 1982
Creator: Meyer, H. R.; Witherspoon, J. P.; McBride, J. P. & Frederick, E. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hydrogen and water reactor safety: proceedings

Description: Separate abstracts were prepared for papers presented in the following areas of interest: 1) hydrogen research programs; 2) hydrogen behavior during light water reactor accidents; 3) combustible gas generation; 4) hydrogen transport and mixing; 5) combustion modeling and experiments; 6) accelerated flames and detonations; 7) combustion mitigation and control; and 8) equipment survivability.
Date: January 1, 1982
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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High-temperature oxidation of Zircaloy in hydrogen-steam mixtures. [PWR; BWR]

Description: Oxidation rates of Zircaloy-4 cladding tubes have been measured in hydrogen-steam mixtures at 1200 to 1700/sup 0/C. For a given isothermal oxidation temperature, the oxide layer thicknesses have been measured as a function of time, steam supply rate, and hydrogen overpressure. The oxidation rates in the mixtures were compared with similar data obtained in pure steam and helium-steam environments under otherwise identical conditions. The rates in pure steam and helium-steam mixtures were equival… more
Date: September 1, 1982
Creator: Chung, H. M. & Thomas, G. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Update: nuclear power program information and data, April-June 1982

Description: UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses prese… more
Date: January 1, 1982
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radioiodine source term and its potential impact on the use of potassium iodide. [PWR; BWR]

Description: Information is presented concerning chemical forms of fission product iodine in the primary circuit; chemical forms of fission product iodine in the containment building; summary of iodine chemistry in light water reactor accidents; and impact of the radiodine source term on the potassium iodide issue.
Date: January 1, 1982
Creator: Malinauskas, A.P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Vaporization of structural materials in severe accidents. [PWR; BWR]

Description: Vaporized structural materials form the bulk of aerosol particles that can transport fission products in severe LWR accidents. As part of the Severe Accident Sequence Analysis (SASA) program at Oak Ridge National Laboratory, a model has been developed based on a mass transport coefficient to describe the transport of materials from the surface of a molten pool. In many accident scenarios, the coefficient can be calculated from existing correlations for mass transfer by natural convection. Data … more
Date: January 1, 1982
Creator: Lorenz, R. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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