A Core hot spot evaluation by statistical method for pool-type sodium-cooled fast reactors, 1; Preliminary applicability assessment of statistical evaluation procedure

Mochinaga, Shota  ; Doda, Norihiro  ; Iwasaki, Takashi*; Igawa, Kenichi*; Tanaka, Masaaki 

We have been developing the core hot spot (CHS) evaluation (e.g., maximum cladding temperature in a fuel pin) for the safety evaluation of a pool-type demonstration sodium-cooled fast reactor (SFR). Since changing analysis conditions due to uncertainty parameters during natural circulation decay heat removal affects the generation of buoyancy, the CHS evaluation based on the statistical method is effective. In this study, CHS evaluation procedure was organized for a pool-type SFR and its applicability was investigated. First trial results of applying the statistical CHS evaluation procedure to the SFR demonstration reactor (tentative specification) during rated operation are reported.