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Petelin, S.; Gortnar, O.; Mavko, B.
First Meeting of the Nuclear Society of Slovenia, Proceedings1992
First Meeting of the Nuclear Society of Slovenia, Proceedings1992
AbstractAbstract
[en] Following the total loss of secondary heat sink in a pressurized water reactor nuclear power plant, the stable decay heat removal can be assured only due to the timely initiation of bleed and feed procedure. In the analysis of this transient for nuclear power plant Krsko was determined the available operator response time to prevent the occurrence of an inadequate core cooling condition and consequential core damage. The analysis aims to evaluate the minimal success criteria for various availabilities of plant safety systems and operator response times. The transient predictions were performed using RELAP5/MOD2 computer code. In this study, particular attention was given to the phenomenological description and explanation of thermal-hydraulic processes, which may take place in system during this accident. (author)
[sl]
V tlacnovodni jedrski elektrarni je mogoce ob izpadu vseh ponorov toplote na sekundarni strani zagotoviti odvod zaostale toplote iz reaktorja le s pravocasnim prehodom na bleed and feed postopek hlajenja. V analizi tega prehodnega pojava za jedrsko elektrarno Krsko smo dolocili mejni cas za operaterjevo posredovanje, ki se omogoca obvladovanje nezgode brez poskodb sredice reaktorja. Cilj analize je dolocitev minimalnih kriterijev uspeha za razlicne predpostavljene razpolozljivosti varnostnih sistemov in razlicne case operaterjevega posredovanja. Uporabljen je bil racunalniski program RELAP5/MOD2. Posebno pozornost smo namenili fenomenoloskemu popisu in razlagi termohidravlicnih procesov, ki med prehodnim pojavom potekajo v sistemih jedrske elektrarne. (author)Original Title
Analiza uspesnosti posegov operaterja med nezgodo z izpadom vseh ponorov toplote na sekundarni strani
Primary Subject
Source
Stritar, A.; Jencic, I. (Nuclear Society of Slovenia (Slovenia)) (eds.); Nuclear Society of Slovenia, Ljubljana (Slovenia); 332 p; ISBN 961-90004-0-4;
; 1992; p. 93-100; First Meeting of the Nuclear Society of Slovenia; Bovec (Slovenia); 11-12 Jun 1992; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (SI); 8 refs., 5 figs.

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Miscellaneous
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Conference
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ACCIDENTS, COMPUTER CODES, COOLING SYSTEMS, ENERGY SYSTEMS, ENRICHED URANIUM REACTORS, FLUID MECHANICS, HYDRAULICS, MECHANICS, POWER REACTORS, PWR TYPE REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SINKS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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