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[en] Four different disturbances during midloop operation of VVER-440/V-213 type reactor have been simulated by experiments in the Hungarian PMK-2 integral-type experimental facility at the KFKI-AEKI (Budapest). Main aims of this type of studies was the determination of the distribution of coolant and noncondensible, coolant temperatures, boiling in the core, etc. Paper presents selected results of the computer modeling of three experiments performed by the RELAP5/MOD3.2.1.2 code. The comparison of test data and calculated results shows that with the INEL developmental code version it was possible to capture most of the important phenomena of interest.(author)
Source
Ravnik, M.; Jencic, I.; Zagar, T. (Nuclear Society of Slovenia, Ljubljana (Slovenia)) (eds.); Nuclear Society of Slovenia, Ljubljana (Slovenia). Funding organisation: European Nuclear Society (Switzerland); Nuclear Power Plant Krsko (Slovenia); Siemens Power Generation Group, Erlangen (Germany); Ministry of Science and Technology of Slovenia, Ljubljana (Slovenia); Institute Jozef Stefan (Slovenia); American Society of Mechanical Engineers (United States); ENCONET Consulting GmbH (Austria); SIAP d.o.o. Pesnica pri Mariboru (Slovenia); Institute for Metal Constructions (Slovenia); Agency for Radwaste management (Slovenia); Slovenian Nuclear Safety Administration (Slovenia); 519 p; ISBN 961-6027-10-5; 
; 1998; p. 187-194; Nuclear Society of Slovenia; Ljubljana (Slovenia); Nuclear Energy in Central Europe 98; Terme Catez (Slovenia); 7-10 Sep 1998; Available from Nuclear Society of Slovenia, Jozef Stefan Institute, Jamova 39, Ljubljana (SI); 16 refs., 2 tabs., 13 figs.
; 1998; p. 187-194; Nuclear Society of Slovenia; Ljubljana (Slovenia); Nuclear Energy in Central Europe 98; Terme Catez (Slovenia); 7-10 Sep 1998; Available from Nuclear Society of Slovenia, Jozef Stefan Institute, Jamova 39, Ljubljana (SI); 16 refs., 2 tabs., 13 figs.