[2G06-09] 過酷事故(Na冷却高速炉)2

[2G08] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(18)Validation of Eutectic Reaction Model for Use in Reactor Safety Analysis Code

*Xiaoxing Liu¹, Koji Morita¹, Hidemasa Yamano² (1. Kyushu Univ., 2. JAEA)

キーワード：sodium-cooled fast recator, core disruptive accident, eutectic reaction, fast reactor safety analysis code

Physical models are developed for the fast recator safety analysis code, SIMMER-III, to simulate the eutectic reaction between stainless steel and boron carbide for assessment of core disruptive accidents of sodium-cooled recators. In this study, numerical simulations were perforemd for a basic experiment on liquefaction of control rod in fast recators, and validity of the physical modelas was examined.