Fauske & Associates, LLC (FAI), Argonne National Laboratory (ANL), and Westinghouse Electric Company LLC (Westinghouse) are collaborating within the program “Development of an Integrated Mechanistic Source Term Assessment Capability for Lead- and Sodium-Cooled Fast Reactors”. This program aims at developing a computational framework for predicting radionuclide release from a broad spectrum of accidents that can be postulated to occur at Liquid-Metal Cooled Reactor (LMR) facilities.This paper discusses the work performed to adapt the SAS4A/SASSYS-1 and FATE codes to LFR technology, the code coupling method, and the results from some LFR test cases.

Additional SAS4a/SASSYS-1 and FATE Topics Covered:

  • Code Coupling
  • Radionuclide Release Model
  • Lead-Cooled Fast Reactor Model
  • Model Testing Results