Steam oxidation of Zr–1.5Nb–0.4Sn–0.2Fe–0.1Cr and Zircaloy-4 at 900–1200°C-Reference-Cited by-同舟云学术

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Steam oxidation of Zr–1.5Nb–0.4Sn–0.2Fe–0.1Cr and Zircaloy-4 at 900–1200°C

Published:2007-03 Issue:1 Volume:361 Page:30-40
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Baek Jong Hyuk,Jeong Yong Hwan

Publisher

Elsevier BV

Subject

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

Reference31 articles.

1. K.S. Lee, Introduction to Nuclear Fuels, Korea, 2001.

2. USNRC-SRP (Standard Review Plan), Sec. 4.2, NUREG-0800.

3. G.P. Sabol, R.J. Comstock, R.A. Weiner, P. Larouere, R.N. Stanutz, Zirconium in the Nuclear Industry, ASTM STP 1245, 1994, p. 724.

4. J.-P. Mardon, D. Charquet, J. Senevat, Zirconium in the Nuclear Industry, ASTM STP 1354, 2000, p. 505.

5. T. Isobe, Y. Matsuo, Zirconium in the Nuclear Industry, ASTM STP 1132, 1991, p. 346.

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