A comparative analysis is made of calculations of a loss-of-coolant accident in a 1500 MW(t) fast reactor. The COREMELT code with different neutron-physical modules RADAR3D and RAKAR2D and the same thermohydraulic module COREMELT are used. The computational results are used as a basis for comparing the self-protection of a reactor with a sodium cavity at the top of the core for the case of a serious accident with coolant boiling. The effect of the diffusion and transport modules of the spatial neutron-physics models on the calculation is analyzed.
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Translated from Atomnaya Énergiya, Vol. 122, No. 4, pp. 183–189, April, 2017.
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Ashurko, Y.M., Volkov, A.V., Raskach, K.F. et al. Neutron-Physical Model Impact on the Calculation of a Serious Accident with Sodium Boiling in a Fast Reactor. At Energy 122, 217–225 (2017). https://doi.org/10.1007/s10512-017-0259-3
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DOI: https://doi.org/10.1007/s10512-017-0259-3