A Core hot spot evaluation by statistical method for pool-type sodium-cooled fast reactors

Mochinaga, Shota  

The conceptual design of a pool-type demonstration sodium-cooled fast reactor (SFR) has been carried out. The core hot spot (CHS) evaluation (e.g., maximum cladding temperature in a fuel pin) considering various uncertainties related to the temperature rise in the core and abnormal transients is required in the safety design. Since changing analysis conditions due to uncertainty parameters 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 poo-type SFR and its applicability was investigated. Establishing the statistical CHS evaluation method with the concrete procedure can ensure reliability of the safety assessment processes and results.