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Effect of biaxial stresses on iodine SCC behavior of zircaloy fuel cladding tubes

  • Published:1982-02 Issue:2-3 Volume:105 Page:159-171
  • ISSN:0022-3115
  • Container-title:Journal of Nuclear Materials
  • language:en
  • Short-container-title:Journal of Nuclear Materials

Author:

Nakatsuka Masafumi,Hayashi Yo

Publisher

Elsevier BV

Subject

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

Reference30 articles.

1. Trans. 5th Intern. Conf. on Structural Mechanics in Reactor Technology;Ranjan,1979

2. Fracture of zirconium alloys in iodine vapour

Cited by 5 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. Mechanical behavior of recrystallized Zircaloy-4 under monotonic loading at room temperature: Tests and simplified anisotropic modeling;Journal of Nuclear Materials;2014-04

2. Development of a Method for Studying the Influence of Stress State on the Iodine-Induced Stress Corrosion Cracking of Zirconium Alloys;15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors;2012-06-26

3. Development of a method for studying the influence of stress state on the iodine-induced stress corrosion cracking of zirconium alloys;Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors;2011

4. Mechanical Properties of Neutron Irradiated Fuel Cladding Tubes;Journal of Nuclear Science and Technology;1991-04

5. Iodine Stress Corrosion Cracking of Zircaloy;CORROSION ENGINEERING;1983
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