Thermo-fluid investigation on a double-side-cooled annular fuel for the prismatic very high temperature gas-cooled reactor-Reference-Cited by-同舟云学术

Thermo-fluid investigation on a double-side-cooled annular fuel for the prismatic very high temperature gas-cooled reactor

Published:2008-10 Issue:10 Volume:238 Page:2821-2827
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Tak Nam-Il,Kim Yonghee,Choi Jae-Hyuk,Lee Won Jae

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference18 articles.

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4. 330MWe Fort St. Vrain high-temperature gas-cooled reactor;Habush;Nucl. Eng. Des.,1968

5. IAEA, 1997. Fuel performance and fission product behaviour in gas cooled reactors. IAEA-TECDOC-978.

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