FACILITY FOR IN-REACTOR CREEP TESTING OF FUEL CLADDING.

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Kohn, E.
Wright, M.G.
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| 1600年
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A biaxial stress creep test facility has been designed and developed for operation in the WR-1 reactor. This report outlines the rationale for its design and describes its construction and the operating experience with it. The equipment is optimized for the determination of creep data on CANDU (Canada Deuterium Uranium) fuel cladding. Typical results from Zr-2. 5 wt. % Nb fuel cladding are used to illustrate the accuracy and reliability obtained.
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