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Bencik, V.; Feretic, D.; Debrecin, N.
Proceedings of the International Conference Nuclear Energy for New Europe 20022002
Proceedings of the International Conference Nuclear Energy for New Europe 20022002
AbstractAbstract
[en] In the paper the results of the NPP Krsko analysis of the loss of the Residual Heat Removal (RHR) system at mid-loop conditions using RELAP5/MOD 3.2.2 Gamma and RELAP5/MOD 3.3 Beta code are presented. Both pressurizer and Steam Generator (SG) 1 manway were open. The facility was open to the containment atmosphere and filled with air above liquid level. Loss of the RHR system when Reactor Coolant System (RCS) is open causes quick boiling in the core and loss of the inventory available for the cooling of the core through the openings. Aims of the analysis were threefold. First, the consequences of the transient for NPP Krsko, i.e., the time to core uncovery was determined. Secondly, the influence of the applied RELAP5 code version (MOD 3.2.2 Gamma and MOD 3.3 Beta) in the analysis of that particular transient with noncondensable gases was assessed. Third, the analysis with SG secondary sides under wet lay-up conditions was performed in order to assess the influence of condensation in the SG U tubes on liquid inventory in the system and core cooling capability.(author)
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Jencic, I.; Tkavc, M. (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); Inst. of Metal Constructions, Ljubljana (Slovenia); NPP Krsko (Slovenia); Framatome, Paris (France); Westinghouse Electric Systems Europe S.A., Brussels (Belgium); Canberra-Packard Central Europe, Schwadorf (Austria); Elmont, Krsko (Slovenia); ENCONET International, Zagreb (Croatia); Inetec, Zagreb (Croatia); NUMIP, Krsko (Slovenia); Q Techna, Krsko (Slovenia); SIAP, Maribor (Slovenia); [602 p.]; ISBN 961-6207-20-2;
; 2002; [10 p.]; International Conference Nuclear Energy in Central Europe 2002; Kranjska Gora (Slovenia); 9-12 Sep 2002; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (SI); 8 refs., 2 tabs., 11 figs.

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ACCIDENTS, BOILERS, COMPUTER CODES, COOLING SYSTEMS, ENERGY SYSTEMS, ENRICHED URANIUM REACTORS, POWER REACTORS, PWR TYPE REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SIMULATION, THERMAL REACTORS, VAPOR GENERATORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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