[1G08-11] Thermal Hydraulics of Sodium-Cooled Fast Reactors 1

[1G09] Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor

(15)Development of multi-level simulation system

*Norihiro Doda¹, Kenji Yokoyama¹, Masaaki Tanaka¹, Takashi Takata¹, Hiroyuki Ohshima¹ (1. JAEA)

Keywords:Sodium cooled fast reactor, coupling analysis, plant dynamics analysis, CFD analysis, Coupled neutronics/thermal-hydraulics calculation

A multi-level plant simulation system in which a one-dimensional plant dynamics system code is coupled with multi-dimensional CFD code, subchannel analysis code, and neutronics analysis code for high-accurate local phenomena analysis has been developed to evaluate various design options of sodium cooled fast reactor as a base technology for safety assessment. Numerical analysis of the EBR-II SHRT-45R test was performed to evaluate the validity of the simulation system. It was confirmed that the numerical analysis with different level of detail by the multi-level simulation could be applied to the evaluation of phenomena of interest in the plant dynamics.