2021 Fall Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 304-1 Thermal Hydraulics, Energy Conversion, Energy Transfer, Energy Storage

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

Wed. Sep 8, 2021 2:45 PM - 4:10 PM Room J

chair: Yoichi Utanohara (INSS)

3:00 PM - 3:15 PM

[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.