Precipitation and growth study of intermetallics and their effect on oxidation behavior in Zr–Sn–Fe

Precipitation and growth study of intermetallics and their effect on oxidation behavior in Zr–Sn–Fe–Cr alloy

Published:2012-11 Issue:1-3 Volume:430 Page:205-215
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Choudhuri G.,Neogy S.,Sen D.,Mazumder S.,Srivastava D.,Dey G.K.,Shah B.K.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference23 articles.

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2. A.M. Garde, G.P. Smith, R.C. Pirek, in: G.D. Moan, P. Rudling (Eds.), 13th Inter. Symp. Zirconium in the Nuclear Industry, ASTM STP 1423, ASTM International, West Conshohocken, PA, 2002, pp. 490–506.

3. Waterside Corrosion of Zirconium Alloys in Nuclear Power Plants, IAEA TECHDOC – 996, pp. 124–169.

4. P. Bossis, D. Pêcheur, K. Hanifi, J. Thomazet, M. Blat, in: 14th Inter. Symp. Zirconium in the Nuclear Industry, STP1467-EB, 2005.

5. G. David, Franklin, P.M. Lang, in: 9th Int. Symp. Zirconium in Nuclear Industry, ASTM-STP-1132 (1991), pp. 3–32.

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