Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan
2012 Fall Meeting
Session ID : P41
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Prismatic HTGR with Silicon Carbide Coated Graphite Block Core: (1) Effects on Thermal-Hydraulic Behavior under the Normal Operation
*Piyatida TRINURUKToru OBARA
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Abstract
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.
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© 2012 Atomic Energy Society of Japan
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