Neutron-Physical Model Impact on the Calculation of a Serious Accident with Sodium Boiling in a Fast Reactor
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DOI: 10.1007/s10512-017-0259-3
Abstract: 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.… read more here.
Keywords: serious accident; sodium; accident; fast reactor ... See more keywords