日本原子力学会 年会・大会予稿集
2011 Fall Meeting
セッションID: N30
会議情報
臨界安全,KUR,高温ガス炉
DESIGN STUDY OF INNOVATIVE SIMPLIFIED SMALL PEBBLE BED REACTOR
(4) ANALYSIS OF THE THORIUM FUEL IN THE SIMPLIFIED PBR DESIGN WITH PEU A PEU FUEL LOADING SCHEME
*DWI IRWANTOTORU OBARA
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会議録・要旨集 フリー

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抄録
Optimization of the fuel use in a small simplified pebble bed reactor with a peu a peu fuel loading scheme have been performed for uranium fuel in the previous study. In the present study, thorium are introduced to the fuel compound and parametric surveys are performed to find the best fuel configuration in order to achieved better burnup characteristics of the reactor system.
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© 2011 Atomic Energy Society of Japan
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