Abstract
A SARCAM (Severe Accident Re-Criticality Assessment Methods) code is under development. It allows data exchange between Severe Accident integral computer code MELCOR and Monte Carlo neutron transport code SERPENT. The basic purpose of this framework is a systematic assessment of the neutron multiplication properties of the molten corium, debris and core remnants, during and after a severe accident in a light water reactor. The paper describes the current status of the methodology development for the lower plenum calculations and provides simulations (test) results for the BWR reactor based on the Fukushima Unit 3 (1F3) design.
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