Abstract
Five standard problems of investigating accidents with loss of coolant in the first loop are studied for the first time on the basis of experiments which were performed in 1993–2001 on the ISB-VVÉR two-circuit integrated thermophysical stand, simulating the first loop of a reactor system with a VVÉR-1000 reactor. The objective of the investigations was to verify the computational thermohydraulic codes developed in this country and abroad – TECh', KORSAR, ATHLET, CATHARE, and RELAP. The results of the verification calculations on the whole agreed well with the experimental data. Most processes and phenomena which can occur in VVÉR-1000 accidents with a small and average-size coolant leak were reproduced in the experiments. Analysis of the results showed that these computational codes can be used to simulate the processes occurring during an accident.
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Blinkov, V.N., Gashenko, M.P., Melikhov, O.I. et al. Computational and Experimental Investigations of Accident Regimes in Standard Problems on the ISB-VVÉR Thermophysical Stand. Atomic Energy 95, 765–770 (2003). https://doi.org/10.1023/B:ATEN.0000016761.51115.dd
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DOI: https://doi.org/10.1023/B:ATEN.0000016761.51115.dd