Shah, P. K.; Dubey, J. S.; Kumar, A.; Shriwastaw, R. S.; Rath, B. N.; Pandit, K. M.; Dhotre, M. P.; Mishra, P.; Alur, V. D.; Anantharaman, S. (PIED)
Source
Journal of Nuclear Materials, 2015. Vol. 460: pp. 1-4
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.