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Szczurek, J.; Fic, A.; Skladzien, J.
Proceedings of the International Conference Nuclear Energy in Central Europe 20012001
Proceedings of the International Conference Nuclear Energy in Central Europe 20012001
AbstractAbstract
[en] The paper is a second part of a study devoted to LOCA plant response analyses for PSA of WWER-440/V213 NPP. The first part was reported at International Conference 'Nuclear Energy in Central Europe 2000'. In order to extend the results obtained for BOHUNICE plant, both existing and new, to be applicable in PSA modeling of PAKS NPP, some comparative analysis have been performed. Both LOCA group limits and accident timing issues were addressed. Analyses are limited to LOCA initiating events with the localization of the break at cold leg non-isolatable pipe segment. Calculations were performed with RELAP5/MOD 3.0 using two versions of input data for BOHUNICE unit 3 and for PAKS NPP. The results can be used to reassess the assumptions used in PSA accident sequence modeling.(author)
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Jencic, I.; Glumac, B. (Nuclear Society of Slovenia (Slovenia)) (eds.); Nuclear Society of Slovenia, Ljubljana (Slovenia). Funding organisation: Inst. Jozef Stefan, Ljubljana (Slovenia); European Nuclear Society, Brussels (Belgium); Ministry of Education, Science and Sport of Slovenia, Ljubljana (Slovenia); Slovenian Nuclear Safety Administration, Ljubljana (Slovenia); Agency for Radwaste Management, Ljubljana (Slovenia); Faculty of Mechanical Engineering, Univ. of Ljubljana (Slovenia); Graduate Program Nucelar Engineering, Univ. of Ljubljana (Slovenia); Inst. of Metals and Technology, Ljubljana (Slovenia); The Inst. of Metal Constructions, Ljubljana (Slovenia); The Milan Vidmar Electroinstitute, Ljubljana (Slovenia); Welding Inst., Ljubljana (Slovenia); NPP Krsko (Slovenia); Framatome, Paris (France); Westinghouse Electric Systems Europe S.A., Brussels (BE); Elmont d.o.o., Krsko (Slovenia); Inetec, Zagreb (Croatia); NUMIP d.o.o, Krsko (Slovenia); Q Techna d.o.o., Krsko (Slovenia); SIAP d.o.o., Krsko (Slovenia); 97.2 Megabytes; ISBN 961-6207-17-2;
; 2001; [7 p.]; International Conference Nuclear Energy in Central Europe 2001; Portoroz (Slovenia); 10-13 Sep 2001; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (Slovenia); 5 refs., 1 tab., 1 fig.

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ACCIDENTS, CALCULATION METHODS, CARBON DIOXIDE COOLED REACTORS, COMPUTER CODES, ENRICHED URANIUM REACTORS, FLUID MECHANICS, GAS COOLED REACTORS, HEAVY WATER MODERATED REACTORS, HWGCR TYPE REACTORS, HYDRAULICS, MECHANICS, NATURAL URANIUM REACTORS, POWER REACTORS, PWR TYPE REACTORS, REACTOR ACCIDENTS, REACTORS, SIMULATION, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS, WWER TYPE REACTORS
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