Effect of Pre-Hydriding on Post-Irradiation Ring-Tensile Properties of Zircaloy-2 Cladding Tubes

Zircaloy-2 tubes were hydrided up to a nominal content of 200 ppm and irradiated as fuel claddings in HBWR. Post-irradiation ring-tensile testing revealed that hydrogen enhances the irradiation-induced decrease of elongation and wall thickness reduction at room temperature. On the other hand, no eff...

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Bibliographic Details
Published inJournal of nuclear science and technology Vol. 13; no. 10; pp. 585 - 590
Main Authors UCHIDA, Masaaki, ICHIKAWA, Michio
Format Journal Article
LanguageEnglish
Published Tokyo Taylor & Francis Group 01.10.1976
Taylor & Francis Ltd
Subjects
elongation
embrittlement
fuel cans
hydrides
hydrogen
hydrogen additions
irradiation
neutron beams
radiation effects
tensile testing
thermal diffusion
thickness
zircaloy-2
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Summary:Zircaloy-2 tubes were hydrided up to a nominal content of 200 ppm and irradiated as fuel claddings in HBWR. Post-irradiation ring-tensile testing revealed that hydrogen enhances the irradiation-induced decrease of elongation and wall thickness reduction at room temperature. On the other hand, no effect of hydrogen was observed on ultimate tensile strength. With testings at 300°C, the effect was negligible on elongation too. From the evaluation of the test results including metallographic observation of ring specimens after fracture, it was concluded that segregation of hydrides due to thermal diffusion of hydrogen during irradiation was at least a part responsible to the above effect of hydrogen enhancing embrittlement.
ISSN:0022-3131
1881-1248
DOI:10.1080/18811248.1976.9734077