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浏览/检索结果: 共7条，第1-7条 帮助 限定条件 发表日期：2020     已选(0)清除 条数/页：5101520253035404550556065707580859095100   排序方式：请选择作者升序作者降序题名升序题名降序发表日期升序发表日期降序提交时间升序提交时间降序 Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants 期刊论文 JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 541, 页码: 10 作者:  Tan, Jibo;  Zhang, Ziyu;  Zheng, Hui;  Wang, Xiang;  Gao, Jun 收藏  |  浏览/下载：18/0  |  提交时间：2021/02/02 Corrosion fatigue  Austenitic stainless steel  High temperature corrosion  Model   Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants 期刊论文 JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 541, 页码: 10 作者:  Tan, Jibo;  Zhang, Ziyu;  Zheng, Hui;  Wang, Xiang;  Gao, Jun 收藏  |  浏览/下载：15/0  |  提交时间：2021/02/02 Corrosion fatigue  Austenitic stainless steel  High temperature corrosion  Model   Electrochemistry and In Situ Scratch Behavior of 690 Alloy in Simulated Nuclear Power High Temperature High Pressure Water 期刊论文 ACTA METALLURGICA SINICA, 2020, 卷号: 56, 期号: 11, 页码: 1474-1484 作者:  Li Xiaohui;  Wang Jianqiu;  Han En-Hou;  Guo Yanjun;  Zheng Hui 收藏  |  浏览/下载：60/0  |  提交时间：2021/02/02 alloy 690  high temperature high pressure water  corrosion  in situ scratch   Electrochemistry and In Situ Scratch Behavior of 690 Alloy in Simulated Nuclear Power High Temperature High Pressure Water 期刊论文 ACTA METALLURGICA SINICA, 2020, 卷号: 56, 期号: 11, 页码: 1474-1484 作者:  Li Xiaohui;  Wang Jianqiu;  Han En-Hou;  Guo Yanjun;  Zheng Hui 收藏  |  浏览/下载：41/0  |  提交时间：2021/02/02 alloy 690  high temperature high pressure water  corrosion  in situ scratch   Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water 期刊论文 ACTA METALLURGICA SINICA-ENGLISH LETTERS, 2020, 页码: 13 作者:  Deng, Ping;  Han, En-Hou;  Peng, Qunjia;  Sun, Chen 收藏  |  浏览/下载：6/0  |  提交时间：2021/02/02 Stainless steel  Irradiation  High-temperature corrosion  Intergranular corrosion   Fretting wear between Alloy 690 and 405 stainless steel in high temperature pressurized water with different normal force and displacement 期刊论文 JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 529, 页码: 14 作者:  Ming, Hongliang;  Liu, Xingchen;  Lai, Jiang;  Wang, Jianqiu;  Gao, Lixia 收藏  |  浏览/下载：43/0  |  提交时间：2021/02/02 Alloy 690  Fretting wear  Normal force  Displacement   Fretting wear between Alloy 690 and 405 stainless steel in high temperature pressurized water with different normal force and displacement 期刊论文 JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 529, 页码: 14 作者:  Ming, Hongliang;  Liu, Xingchen;  Lai, Jiang;  Wang, Jianqiu;  Gao, Lixia 收藏  |  浏览/下载：50/0  |  提交时间：2021/02/02 Alloy 690  Fretting wear  Normal force  Displacement