Abstract
The results of a competition for the development and verification of a more accurate domestic integrated computer code for simulating processes occurring in the containment shell of a nuclear power plant with a VVÉR reactor are examined. The basic requirements for the competing codes, the results of the calculations performed on the basis of the standard safety problem, a comparative analysis of the codes presented, and the steps in the development and verification of the KUPOL-M code are presented.
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REFERENCES
B. I. Nigmatullin, O. I. Melikhov, and S. L. Solov'ev, “State and development of domestic systems thermohydraulic codes for simulating accident and nonstationary processes at a nuclear power plant with VVÉR reactor,” Teploénerg., No. 3, 17-20 (2001).
T. Kanzleiter, J. Gauvain, F. Parozzi, et al., “Future experimental containment facilities in the European Union,” in: Proceedings of Transactions of Concerted Action EUCLFA FISA 99, EU Research in Reactor Safety, Luxemburg (1999).
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Gabaraev, B.A., Efanov, A.D., Zaichik, L.I. et al. Development of an Integrated Computer Code for Simulating Processes Occurring in the Containment Shell of Nuclear Power Plants with VVÉR Reactors. Atomic Energy 91, 517–521 (2001). https://doi.org/10.1023/A:1012409202205
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DOI: https://doi.org/10.1023/A:1012409202205