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AbstractAbstract
[en] In the paper the results of RELAP5/mod3.3 calculations of critical parameters during shutdown for NPP Krsko are presented. Conservative evaluations have been performed at NPP Krsko to determine the minimum configuration of systems required for the safe shutdown operation. Critical parameters in these evaluations are defined as the time to start of the boiling and the time of the core dry-out. In order to have better insight into the available margins, the best estimate code RELAP5/mod3.3 has been used to calculate the same parameters. The analyzed transient is the loss of the Residual Heat Removal (RHR) system, which is used to remove decay heat during shutdown conditions. Several configurations that include open and closed Reactor Coolant System (RCS) were considered in the evaluation. The RELAP5/mod3.3 analysis of the loss of the RHR system has been performed for the following cases: 1) RCS closed and water solid, 2) RCS closed and partially drained, 3) Pressurizer manway open, Steam Generator (SG) U tubes partially drained, 4) Pressurizer and SG manways open, SG U tubes completely drained, 5) Pressurizer manway open, SGs drained, SG nozzle dams installed and 6) SG nozzle dams installed, pressurizer manway open, 1 inch break at RHR pump discharge in the loop with pressurizer. Both RHR trains were assumed in operation prior to start of the transient. The maximum average steady state temperature for all analyzed cases was limited to 333 K. (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); Ministry of Education, Science and Sport of Slovenia, Ljubljana (Slovenia); Westinghouse Electric Europe, Brussels (Belgium); Framatome ANP, Paris (France); NUMIP, Ljubljana (Slovenia); INETEC, Zagreb (Croatia); Agency for Radwaste Management, Ljubljana (Slovenia); Elmont, Krsko (Slovenia); SIAP Analize, Maribor (Slovenia); Slovenian Nuclear Safety Administration, Ljubljana (Slovenia); Faculty of Mechanical Engineering, Univ. of Ljubljana (Slovenia); Inst. of Metals and Technology, Ljubljana (Slovenia); Inst. of Metal Constructions, Ljubljana (Slovenia); Q Techna, Ljubljana (Slovenia); 55.3 Megabytes; ISBN 961-6207-23-7; ; 2004; [8 p.]; International Conference Nuclear Energy for New Europe 2004; Portoroz (Slovenia); 6-9 Sep 2004; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (SI); 10 refs., 2 tabs., 9 figs.
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BOILERS, COMPUTER CODES, COOLING SYSTEMS, ENERGY SYSTEMS, ENGINEERED SAFETY SYSTEMS, ENRICHED URANIUM REACTORS, POWER REACTORS, PWR TYPE REACTORS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTOR PROTECTION SYSTEMS, REACTORS, SHUTDOWN, THERMAL REACTORS, VAPOR GENERATORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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