[2E05-09] Next Generation Reactor Safety 2

[2E08] Development of detailed fuel pin model in SIMMER-V code

(1)Development of the prototype model and verification plan

*Shinya Ishida¹, Hirotaka Tagami¹, Yoshitaka Fukano¹, Hidemasa Yamano¹, Shigenobu Kubo¹ (1. JAEA)

Keywords:Sodium-cooled fast reactor, Severe accident, Core disruptive accident, SIMMER-V code

JAEA has started developing a core disruptive accident analysis code for sodium-cooled fast reactors: SIMMER-V. As a main subject of the development, a prototype of detailed fuel pin model has been developed. This report presents an overview of this model and its verification plan.