Development of a thermal hydraulic analysis code for gas-cooled reactors with annular fuels

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Gas-cooled reactors have been highlighted as a promising option for next generation reactor technology. A thermal hydraulic analysis code for gas-cooled reactors has been developed with a heat transfer model of a block element, which is solved implicitly with the helium energy equation. Validation was carried out through comparison with both experimental and analytical results. A computation module for annular fuel rods has been coupled to the code for comparative analyses of an annular fuel-based block element. At normal operation, the annular fuel shows 80 degrees C lower peak temperature than the solid fuel for the same power in Japan's high temperature engineering test reactor (HTTR), even though the pressure drop is higher in the annular fuel. (C) 2005 Published by Elsevier B.V.
Publisher
ELSEVIER SCIENCE SA
Issue Date
2006-01
Language
English
Article Type
Article
Keywords

PERFORMANCE; STACK; VHTR

Citation

NUCLEAR ENGINEERING AND DESIGN, v.236, no.2, pp.164 - 178

ISSN
0029-5493
DOI
10.1016/j.nucengdes.2005.07.006
URI
http://hdl.handle.net/10203/3341
Appears in Collection
NE-Journal Papers(저널논문)
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