[1D08-13] Thermal Hydraulics of Sodium-Cooled Fast Reactors 2

[1D10] Validation of natural circulation heat removal evaluation method by using EBR-II shutdown heat removal test data

＊Norihiro Doda¹, kennichi igawa², masaki minami², takashi iwasaki², hiroaki ohira¹ (1.JAEA, 2.NESI)

Keywords:Sodium-cooled fast reactor, Natural circulation, EBR-II, Decay heat removal, Validation

Evaluation method for natural circulation heat removal in sodium-cooled fast reactor consisted of plant dynamics code Super-COPD and subchannel analysis code ASFRE has been validated to demonstrate thermal hydraulics in whole primary circuit and coolant temperature distributions in a subassembly under the transient from the rated operation condition to natural circulation condition by using EBR-II shutdown heat removal test 17 (SHRT-17) data.