Hydride Induced Degradation of Mechanical Properties of Zr-2.5Nb Alloy

Author:

Singh R. N.

Publisher

Springer Nature Singapore

Reference25 articles.

1. Singh, R.N., Bind, A.K., Sunil, S., Sarkar, A., Neogy, S., Murty, T.N.: On the evolution of a zirconium alloy for use as pressure tubes in Indian pressurized heavy water reactors. In: Srivatsan, T.S., Karloopia, J.,Gupta, M., Eds., Chapter 5 in the Book titled ‘Advanced Materials for Emerging Applications. Bentham Science Publishers (2023)

2. Singh, R.N., Chaterjee, S., Banerjee, S.: PHWR coolant channel safety issues – a metallurgical perspective. In: First National Conference on ‘Nuclear Reactor Technology – NRT-1’ Nuclear Reactor Safety, Held on November 25-27th, 2002, BARC, Mumbai, India (2002)

3. Lemaignan, C., Motta, A.T.: Zirconium alloys in nuclear applications. Reprint from Materials Science and Technology, A Comprehensive Treatment/edited by RW Cahn, PH Kramer, Chapter 7, from V. 10 B, Nuclear Materials, Part 2, Edited by BR (1993)

4. Cheadle, B.A., Coleman, C.E., Licht, H.: CANDU-PHWR pressure tubes: their manufacture, inspection, and properties. Nucl. Technol.. Technol. 57(3), 413–425 (1982)

5. Singh, R.N., Mukherjee, S., Gupta, A., Banerjee, S.: Terminal solid solubility of hydrogen in Zr-alloy pressure tube materials. J. Alloy. Compd. 389(1–2), 102–112 (2005)

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