Low-cycle corrosion fatigue of Zircaloy-2 in iodine atmospheres
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference24 articles.
1. Fatigue Design Basis for Zircaloy Components
2. The fatigue behaviour of α-zirconium and Zircaloy-2 in the temperature range 20 to 700° C
3. Fatigue life and twinning in alpha-zirconium
4. The role of plastic anisotropy in the fatigue behavior of zircaloy
5. Metallographic studies of fatigue in 20% cold-worked zircaloy-2 containing zirconium hydride
Cited by 9 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
1. The role of stress-state on the low cycle fatigue resistance of non-hydrided beta-treated Zircaloy-4;Journal of Nuclear Materials;2023-04
2. Fractal fatigue crack;Philosophical Magazine;2023-03-25
3. Transformations and cracks in zirconia films leading to breakaway oxidation of Zircaloy;Acta Materialia;2013-06
4. The development of the crack growth model in zirconium claddings in iodine environment;Nuclear Engineering and Design;2002-04
5. Theoretical simulation of the quasistationary crack growth in zirconium claddings in an iodine atmosphere under stress;Atomic Energy;2001
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