Verification Study of the SSC-K Computer Code for Evaluating Inherent Safety of Advanced LMFR

摘要

The Korea Atomic Energy Research Institute (KAERI) is developing the SSC-K code for assessment of the inherent safety features of the advanced LMFR, KALIMER conceptual design, which is a 150 MWe, sodium-cooled, metal-fueled, pool-type reactor. The SSC-K code is fundamentally based on the numerical methods and models of the SSC code, which was originally developed by BNL. Because SSC is only applicable to oxide-fueled, loop-type reactor design, new models for pool thermal-hydraulics, reactivity feedback of metallic fuel, in-core gas expansion module (GEM), two-dimensional hot pool simulation, electro-magnetic pump, passive decay heat removal, and long-term system cooling have been developed for the KALIMER design. A model of sodium boiling in the core is being developed. The SSC-K code is currently being used as the main tool to analyze passive and inherent safety response mechanisms in unprotected events of KALIMER.