| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 7966149 | Journal of Nuclear Materials | 2015 | 4 Pages |
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.
Related Topics
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Nuclear Energy and Engineering
Authors
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,