Results 201 to 210 of about 848 (238)
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A methodology for the estimation of the radiological consequences of a Loss of Coolant Accident
Kerntechnik, 2017Abstract For calculation of the radiological consequences of Large Break Loss of Coolant (LBLOCA) events, a set of various computer codes modeling the corresponding physical processes, disciplines and their appropriate subsequent data exchange are necessary. For demonstrating the methodology applied in MTA EK, a LBLOCA event at shut down
A. Keresztúri +4 more
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An Analysis of Transients in Experiments on Loss-of-Coolant Accidents
Nuclear Science and Engineering, 1976It was found that the results of the RELAP-3 code, which is one of the typical analytical codes for analysis of the loss-of-coolant accident (LOCA) of light water reactors, do not agree well with t...
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Theoretical study on loss of coolant accident of a research reactor
Nuclear Engineering and Design, 2016Abstract Under the design conditions of a research reactor, the siphon phenomenon induced by pipe rupture can cause continuous efflux of water. In order to prevent water efflux, an additional facility is necessary. A siphon breaker is a type of safety facility that can resist the loss of coolant effectively.
Kwon-Yeong Lee, Wan-Soo Kim
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RADIOACTIVITY CONFINEMENT FOR LOSS OF COOLANT ACCIDENTS IN NET
1993This paper provides an overview of confinement pressurization for the case of Loss of Coolant Accidents (LOCAs) occurring during plasma burn as well as during conditioning and baking. The radioactivity confinement strategy is outlined.
Edgar Ebert +2 more
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Identification of Loss-of-Coolant Accidents in LWRs by Inverse Models
Nuclear Technology, 2004This paper describes a novel diagnostic method based on inverse models that could be applied to identification of transients and accidents in nuclear power plants. In particular, it is shown that such models could be successfully applied to identification of loss-of-coolant accidents (LOCAs).
Wojciech Cholewa +2 more
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ARIES-RS loss of coolant accident (LOCA) analysis
17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131), 2002Loss of Coolant Accident (LOCA) analysis has been performed for the ARIES-RS fusion power plant. LOCA occurs when one or more supply tubes outside the reactor are damaged or ruptured preventing the coolant from reaching the in-vessel components. For this analysis, it is assumed that the plasma is immediately quenched and the temperature of the chamber ...
E.A. Mogahed +3 more
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Loss-of-Coolant Accidents in Small Compact Nuclear Reactors
Nuclear Technology, 1979The maximum credible accident for which a nuclear reactor nust be analyzed is a loss-of-coolant accident (LOCA) due to a major rupture in the primary system. Such an accident has been analyzed for a conceptual design of a consolidated nuclear steam system (CNSS) using the thermal-hydraulic computer code RELAP4/MOD5.
R. C. Sanders, G. E. Mueller
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Nuclear Technology, 1998
As part of the AP600 design certification program, a series of component separate effects tests and two integral systems tests of the nuclear steam supply system were performed. These tests were designed to provide data necessary to validate Westinghouse safety analysis codes for AP600 applications.
M. T. Friend +4 more
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As part of the AP600 design certification program, a series of component separate effects tests and two integral systems tests of the nuclear steam supply system were performed. These tests were designed to provide data necessary to validate Westinghouse safety analysis codes for AP600 applications.
M. T. Friend +4 more
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Analysis of multidimensional and countercurrent effects in a BWR loss-of-coolant accident
Nuclear Engineering and Design, 1991Abstract The presence of parallel enclosed channels in a boiling water reactor (BWR) provides opportunities for multiple flow regimes in cocurrent and countercurrent flow under loss-of-coolant accident (LOCA) conditions. To address and understand these phenomena, an integrated experimental and analytical study has been conducted.
B.S. Shiralkar, G.E. Dix, Md. Alamgir
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The Loss-of-Coolant Accident Analysis in Pressurized Water Reactors
Nuclear Science and Engineering, 1969A generalized digital computer approach to analyze the loss-of-coolant accident in pressurized water reactors requires a systematic specification of the plant geometric, physical, and topological c...
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