Design Support and Safety Analysis Calculations for the 400 MWt PG-SFR Advanced Burner Reactor
The Korea Atomic Energy Research Institute (KAERI) and Argonne National Laboratory are jointly designing the Prototype Generation-IV Sodium-Cooled Fast Reactor (PG-SFR). The 400 MWt PG-SFR design concept is intended to test and demonstrate the performance of metal fuel containing transuranics (TRU) for commercial SFRs and the TRU transmutation capability of a burner reactor as part of an advanced fuel cycle. A high level of safety is being designed into the PG-SFR by using metal fuel and simplified safety systems, and focusing on the natural circulation decay heat removal capability of the pool-type primary sodium system.
Argonne and KAERI have both developed conceptual designs for the PG-SFR within the guidelines of the design requirements. Important differences between the two concepts were analyzed and a final joint design is currently being created. In this seminar, design support calculations and safety analyses performed for the PG-SFR concept with the fast reactor safety analysis code SAS4A/SASSYS-1 will be discussed.
These calculations played a key role in determining the locations of the intermediate and decay heat exchangers and verifying the design of the emergency shutdown decay heat removal systems. A model of the reactor protection system (RPS) is currently being developed in SAS4A/SASSYS-1 for simulation of protected transients with the final PG-SFR design. Preliminary results with the RPS model will also be discussed.