Irradiation Embrittlement of Reactor Pressure Vessel Steels: Mechanisms, Models, and Data Correlations
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ASTM International
Cited by 22 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. Study on irradiation embrittlement behavior of reactor pressure vessels by machine learning methods;Annals of Nuclear Energy;2023-11
2. Radiation-enhanced diffusion of copper in iron studied by three-dimensional atom probe;Journal of Nuclear Materials;2021-12
3. Microstructure-Dependent Rate Theory Model of Radiation-Induced Segregation in Binary Alloys;Frontiers in Materials;2021-05-31
4. Pressurized thermal shock analysis of a reactor pressure vessel for optimizing the maintenance strategy: Effect of asymmetric reactor cooling;Nuclear Engineering and Design;2021-03
5. Micromechanical testing of unirradiated and helium ion irradiated SA508 reactor pressure vessel steels: Nanoindentation vs in-situ microtensile testing;Materials Science and Engineering: A;2020-10
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