Author:
Samal M. K.,Balakrishnan K. S.,Parashar J.,Tiwari G. P.
Publisher
Springer Science and Business Media LLC
Reference35 articles.
1. Nikulina A V, Metal Sci Heat Treat 45 (2003) 287.
2. Nikulina A V, Metal Sci Heat Treat 46 (2004) 458.
3. Deshmukh V, Singha U, Tonpe S, Saibaba N, Trans Indian Inst Metals 63 (2010) 397.
4. Edsinger, K., Davies, J.H., and Adamson, R.B. Degraded fuel cladding fractography and fracture behaviour. Zirconium in nuclear industry: 12th International symposium, ASTM STP 1354. G.P. Sabol and G.D. Moan, Eds., American Society for Testing and Materials, West Conshohocken, 2000, 316.
5. Murty K L, Deformation, texture and microstructure—property correlation and in-reactor performance of Zircaloy cladding in LWRs, in Proceedings of the International Symposium on Advances in Zirconium-2002, Sept 11–13, Mumbai, (2002) p 28.
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