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.
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
