[1J05-09] Thermal Hydraulics of Sodium-Cooled Fast Reactors 1

[1J06] Development of fundamental numerical simulation system for integrated safety evaluation in various innovative sodium-cooled fast reactor

(2)Development plan of integrated numerical simulation system for severe accident analysis

*Akihiro Uchibori¹, Ken-ichi Kawada¹, Mitsuhiro Aoyagi¹, Takashi Takata¹, Hirotaka Nakahara², Takashi Abe² (1. JAEA, 2. HGNE)

Keywords:Sodium-cooled fast reactor, Severe Accident, Safety Evaluation, SPECTRA

SPECTRA code has been developed for integrated safety evaluation including severe accident analysis. This paper describes FY2020's results of model advancement of the code and application examination to a PRISM-type reactor as well as four year plan of this study.