Microstructural study of oxide layers formed on Zircaloy-4 in autoclave and in reactor part 11: Impact of the chemical evolution of intermetallic precipitates on their zirconia environment-Reference-Cited by-同舟云学术

Microstructural study of oxide layers formed on Zircaloy-4 in autoclave and in reactor part 11: Impact of the chemical evolution of intermetallic precipitates on their zirconia environment

Published:1995-08 Issue:2 Volume:224 Page:121-130
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Iltis X.,Lefebvre F.,Lemaignan C.

Publisher

Elsevier BV

Subject

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

Reference52 articles.

1. Corrosion of Zirconium Alloys in Nuclear Power Plants,1993

2. Proc. 8th Int. Symp. on Zirconium in the Nuclear Industry;Eucken,1989

3. Proc. 10th Int. Symp. on Zirconium in the Nuclear Industry;Anada,1994

4. A review of microstructure evolution in zirconium alloys during irradiation

5. Proc. 10th Int. Symp. on Zirconium in the Nuclear Industry;Gilbon,1994

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