Thermalhydraulic evaluations for a canflex bundle with natural or recycled uranium fuel in the uncrept and crept channels of a candu-6 reactor /

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Détails bibliographiques
Auteur principal:	Jun, Ji-Su.
Format:	Article
Langue:	English
Sujets:	Bearing-pad height CANFLEX-NU or -RU Bundle CCP Pressure tube creep
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Thư viện lưu trữ:	Thư viện Trường Đại học Đà Lạt

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Thermalhydraulic evaluations for a canflex bundle with natural or recycled uranium fuel in the uncrept and crept channels of a candu-6 reactor /

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