Rupture of spent fuel Zircaloy cladding
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C.K. Chao; K.C. Yang; C.C. Tseng
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Article
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2008
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Elsevier Science
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English
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Delayed hydride cracking in the Zircaloy alloy has been considered as a possible degradation mechanism of spent nuclear fuel cladding in interim dry storage. Some recent in-core fuel failures indicated that a long axial crack developed in the cladding was a secondary failure by delayed hydride crack