[2E09-14] Fast Reactor Thermal Hydraulics

[2E09] FAUST Test Analysis focusing on FP transport Behavior by Core Disruptive Analysis Code, ASTERIA-SFR

*Hiroki Sonoda¹, Tomoko Ishizu¹, Koji Morita² (1. S/NRA/R, 2. Kyushu Univ.)

Keywords:ASTERIA-SFR, Cesium, Source Term, Sodium-cooled Fast Reactor, FAUST Test, ULOF

Methodology of souce term evaluation for ULOF event which is a hypothetical and representative event in safety evaluation of Sodium-cooled Fast Reactors has been developed in S/NRA/R. The abstract will describe outline of analytical models on cesium transfer behavior introduced to ASTERIA-SFR and results on FAUST test analysis conducted for validation.