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浏览/检索结果: 共78条，第1-10条 帮助 条数/页： 5101520253035404550556065707580859095100 排序方式： 请选择提交时间升序提交时间降序发表日期升序发表日期降序题名升序题名降序作者升序作者降序 Stable and Inherited: Technological Strategy and Human Adaptation During 67-30 Thousand Years Ago at the Dashanpo Site in Chengdu Plain, Southwest China 期刊论文  OAI收割 LITHIC TECHNOLOGY, 2025, 页码: 20 作者:  Han, Fang;  Cheng, Liwen;  Huang, Ming;  Yang, Qingjiang;  Zuo, Zhiqiang   |  收藏  |   Evolution of fretting wear behavior of zirconium alloy cladding tube under gross slip regime in simulated primary water of pressurized water reactor 期刊论文  OAI收割 JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2025, 卷号: 220, 页码: 276-289 作者:  Zhang, Yusheng;  Ming, Hongliang;  Wang, Shuji;  Wu, Bin;  Wang, Jianqiu   |  收藏  |   Evolution of fretting wear behavior of zirconium alloy cladding tube under gross slip regime in simulated primary water of pressurized water reactor 期刊论文  OAI收割 JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2025, 卷号: 220, 页码: 276-289 作者:  Zhang, Yusheng;  Ming, Hongliang;  Wang, Shuji;  Wu, Bin;  Wang, Jianqiu   |  收藏  |   Effect of polyacrylic acid on the corrosion behavior of Alloy 690 in pressurized water reactor secondary water 期刊论文  OAI收割 JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2025, 卷号: 220, 页码: 1-13 作者:  Zhang, Zhiyuan;  Zhang, Zhiming;  Wang, Jianqiu;  Ming, Hongliang;  Zhu, Haipeng   |  收藏  |   Comparative corrosion behavior of Alloys 690 and 800 in high-temperature water: Combined effects of polyacrylic acid and dissolved oxygen 期刊论文  OAI收割 CORROSION SCIENCE, 2025, 卷号: 245, 页码: 13 作者:  Zhang, Zhiyuan;  Zhang, Zhiming;  Wang, Jianqiu;  Ming, Hongliang;  Zhu, Haipeng   |  收藏  |   Study of fretting wear behavior of 690TT heat exchanger tube under three fretting regimes in high temperature pressurized water 期刊论文  OAI收割 JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 605, 页码: 11 作者:  Zhang, Yusheng;  Wang, Shuji;  Ming, Hongliang;  Wang, Jianqiu;  Han, En-Hou   |  收藏  |   The role of microstructural evolution in irradiation hardening of Alloy 718 under low dose proton irradiation 期刊论文  OAI收割 JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 606, 页码: 13 作者:  Zhu, Haipeng;  Zhang, Zhiming;  Wang, Jianqiu;  Ming, Hongliang;  Zhang, Zhiyuan   |  收藏  |   The role of microstructural evolution in irradiation hardening of Alloy 718 under low dose proton irradiation 期刊论文  OAI收割 JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 606, 页码: 13 作者:  Zhu, Haipeng;  Zhang, Zhiming;  Wang, Jianqiu;  Ming, Hongliang;  Zhang, Zhiyuan   |  收藏  |   Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints 期刊论文  OAI收割 JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 605, 页码: 13 作者:  Li, Hui;  Li, Gang;  Sun, Wei;  Shao, Xuejiao;  Ma, Guowen   |  收藏  |   Stress corrosion cracking behavior at fusion boundary of cold worked 316LN stainless steel/Inconel 52 M weld joint in simulated primary water environment 期刊论文  OAI收割 CORROSION SCIENCE, 2025, 卷号: 242, 页码: 14 作者:  Sun, Wei;  Wu, Bin;  Ming, Hongliang;  Meng, Fanjiang;  Wang, Jianqiu   |  收藏  |