Effect of pre-hydriding on post-irradiation ring-tensile properties of zircaloy-2 cladding tubes.

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概要

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• 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.

• 一般社団法人 日本原子力学会の論文

著者

• UCHIDA Masaaki

  Tokai Research Establishment, Japan Atomic Energy Research Institute

• ICHIKAWA Michio

  Tokai Research Establishment, Japan Atomic Energy Research Institute

関連論文

• Effect of pre-hydriding on post-irradiation ring-tensile properties of zircaloy-2 cladding tubes.

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