Fracture behavior of irradiated Zircaloy-4 cladding under simulated LOCA conditions

Nagase, Fumihisa ; Fuketa, Toyoshi

To evaluate high burnup fuel behavior under LOCA conditions, integral thermal shock tests were conducted with Zircaloy-4 cladding sampled from PWR fuels, irradited to 39 and 44 GWd/t. Obviou difference was not seen between irradiated and unirradiated cladding specimens in terms of threshold of fractureduring quenching, though the threshold is reduced as initial hydrogen concentration increases. The present result also showed that the threshold of the tested cladding is higher than the limit in the LOCA criteria.

Language	:	English
Journal	:	Journal of Nuclear Science and Technology
Volume	:	43
Number	:	9
Pages	:	p.1114 - 1119
Publication Year/Month	:	2006/09
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Paper URL	:	https://doi.org/10.3327/jnst.43.1114
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Keywords	:	no keyword
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Press Release	:
Article of JAEA R&D Review	:	Is Safety Maintained in Loss-Of-Coolant Accident even with Long-Term Used Fuel?; Evaluation of Light Water Reactor Fuel Behavior under LOCA Conditions[/]
Cooperating Institute	:	国内PWR電力

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Registration No. : AA20050380
JAEA Abstracts No. : 34001191
Paper Submission No. : 1348

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