Effects of Hydride Precipitate Localization and Neutron Fluence on the Ductility of Irradiated Zircaloy-4
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ASTM International
Cited by 12 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. Current Perspectives on Zirconium Use in Light Water Reactor Fuel and Its Continued Use in Nuclear Power;Zirconium in the Nuclear Industry: 20th International Symposium;2023-11-01
2. Investigation on hydrogen embrittlement and failure characteristics of Zr-4 cladding based on the GTN method;Nuclear Materials and Energy;2023-09
3. Experimental Approaches for Manufacturing of Simulated Cladding and Simulated Fuel Rod for Mechanical Decladder;Science and Technology of Nuclear Installations;2020-01-24
4. A comparative study of hydride-induced embrittlement of Zircaloy-4 fuel cladding tubes in the longitudinal and hoop directions;Journal of Nuclear Science and Technology;2017-02-15
5. Studies on Delayed Hydride Cracking of Zircaloy Cladding;Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors;2013-10-04
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