Comparison of modelling the PMK-2 steam generator by codes RELAP and MELCOR
Gyenes, G.; Ezsoel, G.; Perneczky, L.
Second international seminar of horizontal steam generator modelling1993
Second international seminar of horizontal steam generator modelling1993
AbstractAbstract
[en] The RELAP5/MOD2 and MELCOR 1.8.1 codes have been used for simulate the PMK total loss of feedwater with secondary bleed and feed experiments done in a scale-model WWER-440 test facility. Nodalization studies and studies on several-core modelling options were also done. Good agreement was found between the calculations done by RELAP5/MOD2 and MELCOR 1.8.1 JY codes. (orig.) (5 refs., 31 figs.)
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Lukka, M.; Jaervinen, M.; Minkkinen, P.; Ukkola, A.; Levonmaeki, L. (eds.); Lappeenranta Univ. of Technology (Finland); 208 p; ISBN 951-763-788-8; ; 1993; p. 58-88; 2. international seminar on horizontal steam generator modelling; Lappeenranta (Finland); 29-30 Sep 1992
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Report
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Conference
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Descriptors (DEC)
ACCIDENTS, BOILERS, COMPUTER CODES, COOLING SYSTEMS, ENRICHED URANIUM REACTORS, HYDROGEN COMPOUNDS, OXYGEN COMPOUNDS, POWER REACTORS, PWR TYPE REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SIMULATION, STRUCTURAL MODELS, THERMAL REACTORS, VAPOR GENERATORS, WATER, WATER COOLED REACTORS, WATER MODERATED REACTORS
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