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

Akihiro Uchibori

Presentation information

Oral presentation

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

[1G13-18] Thermal Hydraulics in Fast Reactor

Wed. Sep 6, 2023 4:10 PM - 5:50 PM Room G (ES Bildg. 2F ES021)

Chair:Naoya Odaira(Kyoto Univ.)

4:25 PM - 4:40 PM

[1G14] Development of fundamental numerical simulation system for integrated safety evaluation in various innovative sodium-cooled fast reactor

(11)Improvement of simulation system applicability and user convenience

*Akihiro Uchibori¹, Masateru Sonehara¹, Mitsuhiro Aoyagi¹, Yasushi Okano¹, Takashi Takata¹ (1. JAEA)

Keywords:Sodium-cooled fast reactor, Severe Accident, Safety evaluation, Numerical simulation

A base simulation system for integrated safety evaluation of advanced sodium-cooled fast reactors has been developed. In this study, the analysis model for applicability improvement and the user convenience tool are constructed.