Development of a new SSC-K version for the lead-cooled liquid metal reactor analysis

The current version of SSC-K was designed for a sodium cooled, pool type Liquid Meter Reactor (LMR). In development for Generation IV reactors, a lead cooled LMR is one of a strong candidate for the future reactor usually due to the stability of lead. For this reason, it is necessary to secure the safety analysis capability for the potential design of the lead cooled reactor. In this study, therefore, some SSC-K subroutions concerned with coolant thermodynamic properties, have been modified as a basic step to be suited for the lead cooled reactor analysis. The newly modified SSC-K version has been applied to the analysis of TOP(Transient-Over-Power), LOF(Loss Of Flow), LOHS(Loss Of Heat Sink) accidents for a confirmation purpose. The additional developments on the proper correlations as well as other requirements for the lead coolant analysis should be followed to apply the new SSC-K version to the actual lead cooled reactor in the future