SPECIFIC FEATURES OF ALGORITHMS IN THE "EVKLID/V2" CODE FOR NUMERICAL SIMULATION OF MOVING MOLTEN MATERIALIN FAST REACTOR DURING A SEVERE ACCIDENT
E. V. Usov, A. A. Butov, V. I. Chukhno, I. A. Klimonov, I. G. Kudashov, N. A. Pribaturin, N. A. Mosounova, V. F. Strizhov
VANT. Ser.: Mat. Mod. Fiz. Proc 2019. Вып.1. С. 69-77.
To justify safety of advanced reactor plants with a liquid-metal coolant, there is a need in a set of computer codes to simulate severe off-design accidents with core melting. For these purposes, the integral EVKLID/V2 code has been developed at the RAS IBRAE. Its current version allows simulating the behavior of fast-neutron reactors with liquid-metal coolants under stationary and transient operation conditions, as well as their behavior during different design-basis accidents, by carrying out coupled neutron-physical, thermomechanical, and thermal-hydraulic simulations. The SAFR/V1 module has been developed for the simulation of severe accidents in a fast reactor. The module can be run either separately to simulate the melting process for a single fuel element, or within the EVKLID/V2 code that allows simulating the reactor core breakdown with regard to the molten material leakage to a coolant, the transport of components of the broken fuel element to the upper mixing chamber, melting of the fuel assembly can, and the flow passage blocking. Mathematical algorithms of the EVKLID/V2 code used to simulate the thermal breakdown of core are represented in the paper (5 figures, 12 references). Keywords: SAFR/V1, HYDRA-IBRAE/LM, the EVKLID/V2 code, fuel element, core, mathematical modeling, molten mass.
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