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[en] Developed mathematical model was used to study the stage of fuel assembly heating-up with account of oxidation of fuel cans in the CORA-W2 experiment, simulating WWER-1000 core degradation at severe accident. Results of correlation of obtained design characteristics with experimental data for temperatures of fuel cans and casing, as well as for hydrogen generation rate are presented. 10 refs., 9 figs
Journal
[en] Results of simulation and verification of thermohydraulic ATHLET code (Germany) by experimental data of emergency mode of a small leak (2.4 %) from the inlet chamber (down section) of ISB-WWER-1000 integral bench with the circulation pump shutdown and high-pressure water injection to non-emergency (ternary) circuit are presented
Journal
No abstract available
Source
Trufanov, A.A.; Sorokin, A.P. (eds.); Predpriyatie Goskorporatsii Rosatom AO Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii - Fiziko-Ehnergeticheskij Inst. imeni A.I. Lejpunskogo, Obninsk (Russian Federation); 274 p; ISBN 978-5-906512-70-3; 
; 2015; p. 133-135; Thermal physics of new generation reactors (Thermal physics-2015); Teplofizika reaktorov novogo pokoleniya (Teplofizika-2015); Obninsk (Russian Federation); 6-9 Oct 2015; 6 refs., 3 figs.
; 2015; p. 133-135; Thermal physics of new generation reactors (Thermal physics-2015); Teplofizika reaktorov novogo pokoleniya (Teplofizika-2015); Obninsk (Russian Federation); 6-9 Oct 2015; 6 refs., 3 figs.
[en] The mathematical model of the VAPEX-P thermal-hydraulic code for modeling the process of the core melt jet mixing with water at the initial stage of the large-scale vapor explosion in the case of the hypothetical serious accident at the NPP is presented. The results of verifying this code with application of the data on the FARO L-33 experiment, accomplished on the large-scale bench of the United Center of Studies of the European Community, Italy, within the frames of the experimental program of the studies on the core melt jet interaction with water, are indicated
[ru]
Представлена математическая модель теплогидравлического кода VAPEX-P для численного моделирования процесса перемешивания струи расплава активной зоны с водой на начальной стадии крупномасштабного парового взрыва в случае гипотетической тяжелой аварии на АЭС. Приведены результаты верификации этого кода с использованием данных эксперимента FARO L-33, выполненного на крупномасштабном стенде Объединенного Центра Исследований Европейского Сообщества (Италия) в рамках экспериментальной программы исследований взаимодействия расплава активной зоны с водойJournal
[en] Analysis of the L-33 test using VAPEX code was carried out to study the interaction of reactor core melt with water. Mathematical dependences of pressure, temperature of water and gaseous mixture are presented in correlation with experimental data. Results of the calculation accord well with the experiment, which support the adequacy of fragmentation models and film boiling usable in the code. The possibility of the VAPEX code to predict important characteristics of the melt - coolant interaction during reactor accident was shown by means of the analysis
[ru]
С целью изучения взаимодействия расплава активной зоны с водой выполнен анализ эксперимента L-33 с помощью кода VAPEX. Приведены расчетные зависимости давления, температуры воды и газовой смеси в сопоставлении с экспериментальными данными. Результаты расчета хорошо согласуются с экспериментом, что подтверждает адекватность моделей фрагментации и пленочного кипения, используемых в коде. Анализ показал способность кода VAPEX адекватно предсказывать важные характеристики процесса взаимодействия расплава с теплоносителем в ходе развития аварии на АЭСJournal
No abstract available
Source
Trufanov, A.A.; Sorokin, A.P. (eds.); Predpriyatie Goskorporatsii Rosatom AO Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii - Fiziko-Ehnergeticheskij Inst. imeni A.I. Lejpunskogo, Obninsk (Russian Federation); 202 p; ISBN 978-5-906512-82-6; ; 2016; p. 59-61; Thermal physics 2016: Thermal physics of new generation reactors; Teplofizika reaktorov novogo pokoleniya (Teplofizika-2016); Obninsk (Russian Federation); 12-14 Oct 2016; 6 refs., 2 figs.
; 2016; p. 59-61; Thermal physics 2016: Thermal physics of new generation reactors; Teplofizika reaktorov novogo pokoleniya (Teplofizika-2016); Obninsk (Russian Federation); 12-14 Oct 2016; 6 refs., 2 figs.
No abstract available
Source
Trufanov, A.A.; Sorokin, A.P. (eds.); Predpriyatie Goskorporatsii Rosatom AO Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii - Fiziko-Ehnergeticheskij Inst. imeni A.I. Lejpunskogo, Obninsk (Russian Federation); 274 p; ISBN 978-5-906512-70-3; ; 2015; p. 99-101; Thermal physics of new generation reactors (Thermal physics-2015); Teplofizika reaktorov novogo pokoleniya (Teplofizika-2015); Obninsk (Russian Federation); 6-9 Oct 2015; 3 refs., 1 fig.
; 2015; p. 99-101; Thermal physics of new generation reactors (Thermal physics-2015); Teplofizika reaktorov novogo pokoleniya (Teplofizika-2015); Obninsk (Russian Federation); 6-9 Oct 2015; 3 refs., 1 fig.
[en] Assessments of the RELAP5/MOD3.2 computer code using critical heat flux data from three sets of experiments have been performed independently by analysts at the Electrogorsk Research and Engineering Center and the Idaho National Engineering and Environmental Laboratory. The experiments, performed at the KS-1 and V-200 facilities, investigated dryout at the top of rod bundles with geometry typical of VVER reactors. The two assessments were compared, investigating differences in the input models and explaining the resultant differences in the calculations. The differences between the two sets of calculations were generally much smaller than the differences between the calculations and the data. Both assessments found that the code calculations were in minimal agreement with the data, and recommended the development of a more applicable critical heat flux model for the code. (author)
Source
Ravnik, M.; Zagar, T. (Nuclear Society of Slovenia (Slovenia)) (eds.); Nuclear Society of Slovenia, Ljubljana (Slovenia). Funding organisation: Inst. Jozef Stefan, Ljubljana (Slovenia); NUMIP, Krsko (Slovenia); Ministry of Education, Science and Sport of Slovenia, Ljubljana (Slovenia); Westinghouse Electric Systems Europe S.A., Brussels (Belgium); Framatome, Paris (France); Agency for Radwaste Management, Ljubljana (Slovenia); Inetec, Zagreb (Croatia); Elmont, Krsko (Slovenia); Slovenian Nuclear Safety Administration, Ljubljana (Slovenia); Inst. of Metals and Technology, Ljubljana (Slovenia); Inst. of Metal Constructions, Ljubljana (Slovenia); Q Techna, Krsko (Slovenia); Faculty of Mechanical Engineering, Univ. of Ljubljana (Slovenia); Graduate Program Nucelar Engineering, Univ. of Ljubljana (Slovenia); 827 p; ISBN 961-6207-21-0; ; 2003; [6 p.]; International Conference Nuclear Energy for New Europe 2003; Portoroz (Slovenia); 8-11 Sep 2003; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (SI); 3 refs., 5 figs.
; 2003; [6 p.]; International Conference Nuclear Energy for New Europe 2003; Portoroz (Slovenia); 8-11 Sep 2003; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (SI); 3 refs., 5 figs.
[en] The thermal detonation taking into account the microinteraction processes model has been applied to study thermal detonation wave escalation and propagation in the corium-water mixture. Transient escalation stage and subsequent steady-state propagation stage of the thermal detonation have been calculated. The essential decrease of the escalation length in comparison with the previous results calculated without microinteraction concept has been obtained. (author)
Source
Mavko, B.; Cizelj, L.; Kovac, M. (Nuclear Society of Slovenia (Slovenia)) (eds.); Nuclear Society of Slovenia, Ljubljana (Slovenia); Inst. Jozef Stefan, Ljubljana (Slovenia). Funding organisation: Ministry of Science and Technology of Slovenia, Ljubljana (Slovenia); Ministry of Economic Affairs of Slovenia, Ljubljana (Slovenia); European Nuclear Society, Brussels (Belgium); American Society of Mechanical Engineers, New York, NY (United States); NPP Krsko (Slovenia); Westinghouse Electric Systems Europe S.A., Brussels (Belgium); CAE, Toronto (Canada); Siemens AG, Erlangen, Offenbach (Germany); Faculty of Mathematics and Physics, Univ. of Ljubljana (Slovenia); Framatome, Paris (France); Inetec, Zagreb (Croatia); SIAP d.o.o, Pesnica pri Mariboru (Slovenia); IBE d.d. Consulting Engineers, Ljubljana (Slovenia); Inst. of Metals and Technology, Ljubljana (Slovenia); NUMIP d.o.o, Krsko (Slovenia); Q Techna d.o.o., Krsko (Slovenia); Elmont d.o.o., Krsko (Slovenia); Slovenian Nuclear Safety Administration, Ljubljana (Slovenia); Agency for Radwaste Management, Ljubljana (Slovenia); ENCONET Consulting GmbH, Vienna (Austria); The Inst. of Metal Constructions, Ljubljana (Slovenia); The Milan Vidmar Electroinstitute, Ljubljana (Slovenia); Welding Inst., Ljubljana (Slovenia); 13.8 Megabytes; ISBN 961-6303-29-5; ; 2000; [13 p.]; International Conference Nuclear Energy in Central Europe 2000; Bled (Slovenia); 11-14 Sep 2000; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (SI); 18 refs., 5 figs.
; 2000; [13 p.]; International Conference Nuclear Energy in Central Europe 2000; Bled (Slovenia); 11-14 Sep 2000; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (SI); 18 refs., 5 figs.
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