Thermal hydraulics of sodium-cooled fast reactors; Key design and safety issues and highlights

Ninokata, Hisashi*; Kamide, Hideki 

In this paper key issues and highlighted topics in thermal hydraulics are discussed in the current Japan's sodium-cooled fast reactor development efforts. In particular, design study and related researches of the Japan Sodium-cooled Fast Reactor (JSFR) are focused. Several innovative technologies, e.g., fully natural circulation decay heat removal and recriticality-free core, have been investigated in order to reduce construction cost and to achieve higher level of reactor safety. Preliminary evaluations of innovative technologies to be applied to JSFR are on-going. Here, progress of design study is introduced. Then, research and development activities are briefly reviewed.