Oxidation of Zircaloy-2 and Zircaloy-4 in water and lithiated water at 360°C-Reference-Cited by-同舟云学术

Oxidation of Zircaloy-2 and Zircaloy-4 in water and lithiated water at 360°C

Published:2001-05 Issue:1 Volume:295 Page:97-108
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Oskarsson M.,Ahlberg E.,Pettersson K.

Publisher

Elsevier BV

Subject

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

Reference38 articles.

1. E. Hillner, J.N. Chirigos, The Effect of Lithium Hydroxide and Related Solutions on the Corrosion Rate of Zircaloy in 680 F Water, Bettis Atomic Power Laboratory, Pittsburgh, PA, Contract AT-11-1-GEN-14, 1962

2. Corrosion characteristics and oxide microstructures of Zircaloy-4 in aqueous alkali hydroxide solutions

3. N. Ramasubramanian, N. Precoanin, V.C. Ling, in: L.F.P.V. Swam, C.M. Eucken (Eds.), Zirconium in the Nuclear Industry: Eighth International Symposium, Vol. ASTM STP 1023, Philadephia, PA, 1989, p. 187

4. Dissolution of zirconium oxide films in 300°C LiOH

5. B. Cox, M. Ungurela, Y.-M. Wong, C. Wu, in: E.R. Bradley, G.P. Sabol (Eds.), Zirconium in the Nuclear Industry: 11th International Symposium, Vol. ASTM STP 1295, Garmisch-Partenkirchen, Germany, 1996, p. 114

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