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The role of microstructural evolution in irradiation hardening of Alloy 718 under low dose proton irradiation 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 606, 页码: 13
作者:  Zhu, Haipeng;  Zhang, Zhiming;  Wang, Jianqiu;  Ming, Hongliang;  Zhang, Zhiyuan;  Jiang, Yilan;  Ren, Quanyao;  Han, En-Hou
收藏  |  浏览/下载:2/0  |  提交时间:2025/04/27
Low dose proton irradiation  Alloy 718  Microstructure  Irradiation hardening  
The role of microstructural evolution in irradiation hardening of Alloy 718 under low dose proton irradiation 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 606, 页码: 13
作者:  Zhu, Haipeng;  Zhang, Zhiming;  Wang, Jianqiu;  Ming, Hongliang;  Zhang, Zhiyuan;  Jiang, Yilan;  Ren, Quanyao;  Han, En-Hou
收藏  |  浏览/下载:1/0  |  提交时间:2025/04/27
Low dose proton irradiation  Alloy 718  Microstructure  Irradiation hardening  
Microstructure evolution in titanium carbide with different stoichiometry under 3 MeV Au2+ ion irradiation 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 606, 页码: 12
作者:  Shi, Jinyu;  Lei, Yiming;  Wang, Chenxu;  Zhang, Jie;  Wang, Jingyang
收藏  |  浏览/下载:3/0  |  提交时间:2025/04/27
Titanium carbide ceramics  Ion irradiation  Amorphization resistance  Ordered phases  Twins  
Study of fretting wear behavior of 690TT heat exchanger tube under three fretting regimes in high temperature pressurized water 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 605, 页码: 11
作者:  Zhang, Yusheng;  Wang, Shuji;  Ming, Hongliang;  Wang, Jianqiu;  Han, En-Hou
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Fretting regime  Running condition fretting map  Material response fretting map  690tt heat exchanger tube  High temperature pressurized water  
Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 605, 页码: 13
作者:  Li, Hui;  Li, Gang;  Sun, Wei;  Shao, Xuejiao;  Ma, Guowen;  Ming, Hongliang;  Zhu, Yichao
收藏  |  浏览/下载:2/0  |  提交时间:2025/04/27
Pressurised water stress corrosion cracking  Inconel 690 alloy  690 weld joints  Crack growth rate  Dynamics model  Crack initiation  
Effect of cold work level on the crack propagation behaviour of 316LN stainless steel in high-temperature pressurized water 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 603, 页码: 17
作者:  Sun, Wei;  Wu, Bin;  Ming, Hongliang;  Wang, Jianqiu;  Han, En-Hou
收藏  |  浏览/下载:2/0  |  提交时间:2025/04/27
316LN stainless steel  Cold work  Stress corrosion cracking  High-temperature pressurized water  Crack propagation  
Effect of cold work level on the crack propagation behaviour of 316LN stainless steel in high-temperature pressurized water 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 603, 页码: 17
作者:  Sun, Wei;  Wu, Bin;  Ming, Hongliang;  Wang, Jianqiu;  Han, En-Hou
收藏  |  浏览/下载:2/0  |  提交时间:2025/04/27
316LN stainless steel  Cold work  Stress corrosion cracking  High-temperature pressurized water  Crack propagation  
Enhancing corrosion resistance of T91 F/M steel in liquid lead-bismuth (LBE) by slurry FeAl coating 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 603, 页码: 9
作者:  Wang, Wen;  Yang, Liujie;  Qian, Hongchen;  Zhu, Zhaoguang;  Zhu, Guangjian;  Tan, Jibo;  Huang, Jinyang;  Lu, Jintao;  Kuang, Wenjun
收藏  |  浏览/下载:2/0  |  提交时间:2025/04/27
T91 steel  Slurry aluminizing  Fe-Al coating  Lead-bismuth eutectic  Liquid metal corrosion  
Thermal corrosion behavior of Inconel 693, Hastelloy N and 310S in ceramic waste forming reactions (vol 603, 155416, 2025) 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 604, 页码: 1
作者:  Ge, Zongyao;  Tan, Shengheng;  Li, Yingju;  Bao, Liangjin;  Feng, Xiaohui;  Liu, Tianyu;  Yang, Yuansheng
收藏  |  浏览/下载:1/0  |  提交时间:2025/04/27
Effects of coolant pH on crud deposition behavior on fuel cladding tube under subcooled nucleate boiling condition in high temperature pressurized water 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 603, 页码: 13
作者:  Lin, Zihao;  Zhang, Ziyu;  Tan, Jibo;  Wu, Xinqiang
收藏  |  浏览/下载:1/0  |  提交时间:2025/04/27
Crud deposition  Fuel cladding tube  Coolant pH  Subcooled nucleate boiling  Solubility