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Skerlavaj, A.; Mavko, B.; Kljenak, I.
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 test E11.2 'Hydrogen distribution in loop flow geometry', which was performed in the Heissdampf Reaktor containment test facility in Germany, was simulated with the CONTAIN computer code. The predicted pressure history and thermal stratification are in relatively good agreement with the measurements. The compositional stratification within the containment was qualitatively well predicted, although the degree of the stratification in the dome area was slightly underestimated. The analysis of simulation results enabled a better understanding of the physical phenomena during the test.(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; [11 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); 8 refs., 12 figs.

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BWR TYPE REACTORS, CALCULATION METHODS, COMPUTER CODES, ELEMENTS, ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, FLUID FLOW, NONMETALS, NUCLEAR FACILITIES, POWER PLANTS, POWER REACTORS, REACTORS, RESEARCH AND TEST REACTORS, SIMULATION, THERMAL POWER PLANTS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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