UO2/Zry-4 chemical interaction layers for intact and leak PWR fuel rods-Reference-Cited by-同舟云学术

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UO2/Zry-4 chemical interaction layers for intact and leak PWR fuel rods

Published:2010-09 Issue:2 Volume:404 Page:128-137
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Kim Kyu-Tae

Publisher

Elsevier BV

Subject

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

Reference16 articles.

1. Dissolution of uranium dioxide by molten zircaloy

2. Dissolution of uranium dioxide by molten zircaloy

3. Dissolution of solid UO2 fuel by molten zircaloy-4 Cladding, in: Severe Fuel Damage Program Review Meeting;Hofmann,1986

4. Dissolution of UO2 by molten zircaloy-4 cladding, in: Fifth International Conference on Thermal Nuclear Reactor Safety;Rosinger,1984

5. P.J. Hayward, I.M. George, J. Nucl. Mater. 232(1996)1–12.

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