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浏览/检索结果: 共8条，第1-8条 帮助 限定条件 学科主题：Nuclear Science & Technology    专题：金属研究所    第一署名单位    第一作者单位    通讯作者单位     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 Influence of graphite-alloy interactions on corrosion of Ni-Mo-Cr alloy in molten fluorides 期刊论文 JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 503, 页码: 116-123 作者:  Ai, H;  Hou, J;  Ye, XX;  Zeng, CL;  Sun, H 收藏  |  浏览/下载：38/0  |  提交时间：2018/06/05 Flinak Salt Environments  Moisture   Energetics analysis of interstitial loops in single-phase concentrated solid-solution alloys 期刊论文 JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 501, 页码: 94-103 作者:  Wang, XX;  Niu, LL;  Wang, SQ;  Wang, XX (reprint author), Chinese Acad Sci, Inst Met Res, Shenyang Natl Lab Mat Sci, Shenyang 110016, Liaoning, Peoples R China. 收藏  |  浏览/下载：24/0  |  提交时间：2018/06/05 Stacking-fault Energy  Radiation-induced Segregation  High-entropy Alloys  Ab-initio Calculations  Ni-based Alloys  Molecular-dynamics  Defect Evolution  Fcc Metals  Gamma-fe  Irradiation   Structural, mechanical and corrosion studies of Cr-rich inclusions in 152 cladding of dissimilar metal weld joint 期刊论文 JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 498, 页码: 9-19 作者:  Li, YF;  Wang, JQ;  Han, EH;  Yang, CD;  Wang, JQ (reprint author), Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Liaoning, Peoples R China. 收藏  |  浏览/下载：35/0  |  提交时间：2018/06/05 Pressurized-water Reactors  Environmentally-assisted Cracking  Safe-end  Quantitative Assessment  Secondary-side  Residual-stresses  High-temperature  Fusion Boundary  Base Alloys  Part 1   Tensile properties and microstructure of Zr-1.8Nb alloy subjected to 140-MeV C4+ ion irradiation 期刊论文 ELSEVIER SCIENCE BV, 2017, 卷号: 495, 页码: 138-145 作者:  Yang, H. L.;  Kano, S.;  Matsukawa, Y.;  Shen, J. J.;  Zhao, Z. S. 收藏  |  浏览/下载：226/0  |  提交时间：2018/01/10 Zr-nb Alloy  High Energy Ion irradiatIon  Dislocation Loops  Mechanical Properties  Strengthening   Multiaxial ratcheting behavior of zirconium alloy tubes under combined cyclic axial load and internal pressure 期刊论文 JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 489, 页码: 99-108 Chen, G.; Zhang, X.; Xu, D. K.; Li, D. H.; Chen, X.; Zhang, Z. 收藏  |  浏览/下载：29/0  |  提交时间：2017/08/17 Zirconium alloy  Multiaxial loading  Ratcheting  Loading history  Microstructure   Strong trapping and slow diffusion of helium in a tungsten grain boundary 期刊论文 JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 487, 页码: 158-166 Wang, Xin-Xin; Niu, Liang-Liang; Wang, Shaoqing 收藏  |  浏览/下载：20/0  |  提交时间：2017/08/17 Grain boundary  Helium  Segregation  Diffusion  Tungsten   Effect of cold rolling on the oxidation resistance of T91 steel in oxygen-saturated stagnant liquid lead-bismuth eutectic at 450 degrees C and 550 degrees C 期刊论文 JOURNAL OF NUCLEAR MATERIALS, 2016, 卷号: 476, 页码: 213-217 Dong, Hong; Ye, Zhongfei; Wang, Pei; Li, Dianzhong; Zhang, Yutuo; Li, Yiyi 收藏  |  浏览/下载：40/0  |  提交时间：2016/08/22 Lead-bismuth eutectic  Martensitic steel  Cold rolling  Non-equilibrium grain boundary  Migrating dislocation   Effects of temperature and strain rate on the tensile behaviors of SIMP steel in static lead bismuth eutectic 期刊论文 JOURNAL OF NUCLEAR MATERIALS, 2016, 卷号: 473, 页码: 189-196 Liu, Jian; Yan, Wei; Sha, Wei; Wang, Wei; Shan, Yiyin; Yang, Ke 收藏  |  浏览/下载：16/0  |  提交时间：2016/08/22 Electron microscopy  Light microscopy  LBE  Steel  Oxidation