日本原子力学会 年会・大会予稿集
2012 Fall Meeting
セッションID: P41
会議情報

Prismatic HTGR with Silicon Carbide Coated Graphite Block Core: (1) Effects on Thermal-Hydraulic Behavior under the Normal Operation
*TRINURUK PiyatidaOBARA Toru
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会議録・要旨集 認証あり

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抄録
Enhancing passive safety in HTGR by SiC coating can cause an increase of the fuel temperature in the reactor core because of poor thermal conductivity of SiC as compared to graphite. However, the maximum fuel temperature can be acceptable management under the criteria of TRISO coated fuel particle by the appropriate design of the reactor system operation.
著者関連情報
© 2012 Atomic Energy Society of Japan
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