OUTLINE OF RESEARCH AND DEVELOPMENT OF THERMAL-HYDRAULICS AND SAFETY OF JAPANESE SUPERCRITICAL WATER COOLED REACTOR (JSCWR) PROJECT
The 5th International Symposium on SuperCritical Water-cooled Reactors - 2011 March 13-16


Presented at:
The 5th International Symposium on SuperCritical Water-cooled Reactors
2011 March 13-16
Location:
Vancouver,Canada
Session Title:
General Thermalhydraulics & Safety

Authors:
Toru Nakatsuka (Japan Atomic Energy Agency)
Hideo Mori (Kyushu University)
Miyuki Akiba (Toshiba Corporation)
Koichiro Ezato (Japan Atomic Energy Agency)
Makoto Yasuoka (Toshiba Corporation)
  

Abstract

In the thermal-hydraulic area of Japanese Supercritical Water Cooled Reactor project (JSCWR), the main objective is to provide high-precision heat transfer and hydraulics resistance correlations of supercritical water which are necessary for the conceptual design of the core and fuel. For this purpose, a database was constructed from literature survey and previous research results. The most suitable correlation applied for circular tubes was selected based on the database and the range of application and predictive accuracy were defined. A thermal-hydraulics analysis code has started to be developed based on large eddy simulation, which is selected for simulation of the heat transfer deterioration, to give detailed information of thermal-hydraulics phenomena in a fuel bundle.

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