中国科学院机构知识库网格系统: 检索

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	Editorial: Nuclear materials degradation 期刊论文 OAI收割 FRONTIERS IN MATERIALS, 2023, 卷号: 10, 页码: 2 作者: Ming, Hongliang; Zhang, Zhiming; Chen, Jian; Noel, James J. \| 收藏 \| 浏览/下载：6/0 \| 提交时间：2024/01/07 nuclear material corrosion stress corrosion cracking irradiation materials for advanced reactors
	Effect of Surface State on Corrosion and Stress Corrosion for Nuclear Materials 期刊论文 OAI收割 ACTA METALLURGICA SINICA, 2023, 卷号: 59, 期号: 4, 页码: 513-522 作者: Han En-Hou \| 收藏 \| 浏览/下载：5/0 \| 提交时间：2024/01/07 surface state corrosion stress corrosion irradiation-assisted stress corrosion nuclear material stainless steel nickel-based alloy
	Research Progress on the Corrosive Environment Large-Scale Evolution for Nuclear Waste Container 期刊论文 OAI收割 FRONTIERS IN MATERIALS, 2022, 卷号: 9, 页码: 10 作者: Zhang, Qichao; Jiang, Yishan; Zhao, Xin; Chen, Juna; Xia, Dahai \| 收藏 \| 浏览/下载：26/0 \| 提交时间：2022/11/11 metal corrosion nuclear waste environment evolution radiation buffer material
	Recent research progress on the compatibility of tritium breeders with structural materials and coatings in fusion reactors 期刊论文 OAI收割 TUNGSTEN, 2022, 卷号: 4 作者: Gu Shouxi; Qi Qiang; Chen Lei; Zhou Haishan; Liu Songlin \| 收藏 \| 浏览/下载：8/0 \| 提交时间：2023/11/10 Nuclear fusion Tritium breeder Compatibility Blanket material
	Preparation of ultrafine-grained/nanostructured tungsten materials: An overview 期刊论文 OAI收割 JOURNAL OF ALLOYS AND COMPOUNDS, 2019, 卷号: 779, 期号: 无, 页码: 926-941 作者: Wu, Yu-Cheng; Hou, Qing-Qing; Luo, Lai-Ma; Zan, Xiang; Zhu, Xiao-Yong \| 收藏 \| 浏览/下载：25/0 \| 提交时间：2020/05/21 Ultrafine-grained/nanostructure tungsten Plasma-facing material Nuclear fusion reactor
	Interplay of solute-mixed self-interstitial atoms and substitutional solutes with interstitial and substitutional helium atoms in tungsten-transition metal alloys 期刊论文 OAI收割 NUCLEAR FUSION, 2019, 卷号: 59, 期号: 2, 页码: 10 作者: You, Yu-Wei; Sun, Jingjing; Wu, Xuebang; Xu, Yichun; Zhang, Tao \| 收藏 \| 浏览/下载：82/0 \| 提交时间：2019/12/25 tungsten-transition metal alloys alloying solutes mixed self-interstitial atoms helium clustering nuclear fusion plasma-facing material
	Evaluation of Fatigue Properties of CA6NM Martensite Stainless Steel Using Miniature Specimens 期刊论文 OAI收割 ACTA METALLURGICA SINICA, 2018, 卷号: 54, 期号: 10, 页码: 1359-1367 作者: Ma Yefei; Song Zhuman; Zhang Siqian; Chen Lijia; Zhang Guangping \| 收藏 \| 浏览/下载：27/0 \| 提交时间：2021/02/02 martensite stainless steel fatigue property miniature specimen size effect nuclear power material
	Developing the science and technology for the Material Plasma Exposure eXperiment 期刊论文 OAI收割 NUCLEAR FUSION, 2017, 卷号: 57, 期号: 11 作者: Rapp, J.; Biewer, T. M.; Bigelow, T. S.; Caneses, J. F.; Caughman, J. B. O. \| 收藏 \| 浏览/下载：48/0 \| 提交时间：2018/08/16 Plasma Material Interactions Linear Plasma Devices Divertor Nuclear Materials
	A Simulation Study on the Temperature Response of W/Cu Divertor Monoblocks under High Heat Fluxes 会议论文 OAI收割作者: Li, Chun; Zhao, Si-Xiang; Ma, Shi-Yu; Liu, Wei; Zhu, Yuan-Zhi \| 收藏 \| 浏览/下载：27/0 \| 提交时间：2018/08/20 Nuclear material W/Cu divertor monoblock Temperature High heat flux