Keynote - Thermalhydraulics of Sodium-Cooled Fast Reactors - Key Issues and Highlights
NURETH-14 - 2011 September 25-30


Presented at:
NURETH-14
2011 September 25-30
Location:
Toronto, Canada
Session Title:
Keynote Lectures Tuesday 1

Authors:
Hisashi Ninokata (Tokyo Institute of Technology)
Hideki Kamide (Japan Atomic Energy Agency)
  

Abstract



In this paper key issues and highlighted topics in thermal hydraulics are discussed in connection to 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., compact reactor vessel, two-loop system, 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 on the thermal hydraulics related to the innovative technologies are briefly reviewed.

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