[2F05-09] Fast Reactor Thermal Hydraulics 1

[2F07] Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor

(12)Fundamental experiment on sodium-concrete reaction (second report)

*Shin Kikuchi¹, Nobuyoshi Koga², Akikazu Kurihara¹, Takashi Takata¹, Hiroyuki Ohshima¹ (1. JAEA, 2. Hiroshima Univ.)

Keywords:sodium-cooled fast reactor, sodium-concrete reaction, thermal analysis

Multi-level, multi-scenario simulation systems as safety fundamental technology for sodium-cooled fast reactors (SFRs) has been developed. In this report, the results of fundamental experiment on sodium-concrete reaction as specific safety issue of SFR for code V&V is presented.