Chemically assisted crack nucleation in zircaloy
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference40 articles.
1. Chemical interactions between simulated fission products and zircaloy-4 at elevated temperatures, including influence on ductility and time-to-failure
2. Paper presented at the IAEA Specialists' Meeting on Pellet-Cladding Interaction;Nagai,1983
3. Paper presented at IAEA Specialists Meeting on Pellet-Cladding Interaction in Water Reactors;Une,1980
4. Fracture mechanics analysis of iodine-induced crack growth in Zircaloy-4 tubing between 500 and 700°C
5. The iodine-induced strain rate sensitivity of Zircaloy fuel rod cladding
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1. The effect of iodine content and specimen orientation on stress corrosion crack growth rate in Zircaloy-4;Corrosion Science;2010-06
2. Strain-hardening influence on iodine induced stress corrosion cracking of Zircaloy-4;Journal of Nuclear Materials;2008-02
3. Stress-corrosion crack initiation and propagation behavior of Zircaloy-4 cladding under an iodine environment;Journal of Nuclear Materials;2008-01
4. Crack initiation and propagation behavior of zirconium cladding under an environment of iodine-induced stress corrosion;Metals and Materials International;2007-03
5. Modélisation de l'endommagement intergranulaire des gaines de combustibles en condition d'interaction pastille-gaine;Le Journal de Physique IV;2001-04
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