FEASIBILITY STUDY FOR DESIGN OF FUEL ROD IN JSCWR
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:
Fuel Design (I)

Authors:
Shinichi Higuchi (Toshiba Corporation)
Shungo Sakurai (Toshiba Corporation)
Katsumi Yamada (International Atomic Energy Agency)
Yuki Ishiwatari (University of Tokyo)
  

Abstract

On the basis of the core and fuel design, as well as for safety analyses and material development established in the JSCWR, the thermo-mechanical behavior of typical fuel rods was evaluated to study the feasibility for design of fuel rods. Analyses showed that stress, cumulative creep damage on the cladding and fuel centerline temperature were able to be within the respective design limits. It was found that the long term cumulative creep damage effect in normal operating played an important role in the feasibility evaluation because of high temperature of the cladding and stress from large pressure difference between inner and outer of the fuel.

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