Delayed hydride crack growth study on irradiated Zr–2.5Nb pressure tube

Priti Kotak Shah; J.S. Dubey; Ashwini Kumar; R.S. Shriwastaw; B.N. Rath; K.M. Pandit; M.P. Dhotre; P. Mishra; V.D. Alur; S. Anantharaman

doi:10.1016/j.jnucmat.2015.01.046

journal article·2015-05

Delayed hydride crack growth study on irradiated Zr–2.5Nb pressure tube

Priti Kotak Shah, J.S. Dubey, Ashwini Kumar, R.S. Shriwastaw, B.N. Rath, K.M. Pandit, M.P. Dhotre, P. Mishra, V.D. Alur, S. Anantharaman

Journal of Nuclear Materials· Volume 460

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Abstract

Abstract Delayed hydride crack (DHC) growth study was carried out on irradiated Indian Zr–2.5Nb pressure tube which had seen around 8 effective full power years of operation. Disc compact tension type specimens were used for the DHC tests at 210 °C, 250 °C, 265 °C and 290 °C. This paper discusses the test methodology, results generated and compares it with that obtained on the as-fabricated pressure tube of similar specification.

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OpenAlex topics: Nuclear Materials and Properties · Nuclear and radioactivity studies · Nuclear reactor physics and engineering

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