The application of the BAGIRA code for a computational analysis of accident conditions involving a small leak from the reactor coolant circuit on the PSB-VVER test facility

A. N. Veselovskii, A. F. Zhivotyagin, A. E. Kroshilin, and V. E. Kroshilin, “Analysis of Three-Dimensional Flows of Nonequilibrium Two-Phase Mixtures,” Teploenergetika, No. 5, 26–31 (1995) [Therm. Eng., 42 (5) (1995)].

A. N. Veselovskii, A. F. Zhivotyagin, S. D. Kalinichenko, et al., “The Program System BAGIRA for Simulation Thermohydrodynamics of Multiphase Media,” Teploenergetika, No. 5, 11–16 (1998) [Therm. Eng., 45 (5) 361–366 (1998)].

A. E. Kroshilin, V. E. Kroshilin, A. V. Smirnov, et al., “An Integral Program System for Assessing the Safety of Nuclear Power Stations”, Teploenergetika, No. 1, 15–21 (2001) [Therm. Eng., 48 (1) 14–20 (2001)].

S. D. Kalinichenko, A. E. Kroshilin, V. E. Kroshilin, and A. V. Smirnov, “Experience in Verifying the Thermohydraulic Program System BAGIRA on the Integral Safety Test Bed for VVER Reactors,” Teploenergetika, No. 11, 10–15 (2003) [Therm. Eng., 50 (11), 883–888 (2003)].

A. E. Kroshilin, V. E. Kroshilin, and A. V. Smirnov, “Numerical Simulation of Experiments with Leaks of Coolant from the Reactor Coolant Circuit on the PSB-VVER Test Facility Using the BAGIRA Software System,” Teploenergetika, No. 12, 15–22 (2005) [Therm. Eng., 52 (12), 918–924 (2005)].

O. Melikhov, V. Melikhov, Yu. Parfenov, et al., “Analysis of the VVER Standard Problem INSC-PSBV1 “11% Coolant Leak from Upper Plenum” with RELAP5/MOD3.2,” in Proceedings of 2004 International Conference on Advances in Nuclear Power Plants (ICAAPP’04), Pittsburgh, PA, United States, June 13–17, 2004, Paper 4188.