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浏览/检索结果: 共9条，第1-9条 帮助 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 Startup Thermal Analysis of a Supercritical-Pressure Light Water-Cooled Reactor CSR1000 期刊论文 Frontiers in Energy Research, 2018, 卷号: 6 作者:  Yuan, Yuan;  Shan, Jianqiang;  Wang, Li;  Wang, Dongqing;  Zhang, Xiaoying 收藏  |  浏览/下载：3/0  |  提交时间：2019/11/26 Generation IV nuclear energy systems  Maximum cladding surface temperatures  Once-through direct cycle  SCTRAN  Start-up characteristics  State-of-the-art methods  Super-critical pressures  Supercritical water reactors   Analysis of complete loss of forced flow accident in china super-critical water reactor 期刊论文 Hedongli Gongcheng/Nuclear Power Engineering, 2013, 卷号: 34, 期号: [db:dc_citation_issue], 页码: 83-86 作者:  Zhang, Dan;  Lu, Jian-Chao;  Liu, Song-Tao;  Shan, Jian-Qiang 收藏  |  浏览/下载：2/0  |  提交时间：2019/12/03 APROS  CRS1000  Forced flows  Loss of feed water  Passive  Passive residual heat removal system  Safety condition  Supercritical water reactors   Development of safety analysis code for SCWR 期刊论文 Hedongli Gongcheng/Nuclear Power Engineering, 2013, 卷号: 34, 期号: [db:dc_citation_issue], 页码: 92-96 作者:  Wu, Pan;  Dang, Gao-Jian;  Gou, Jun-Li;  Shan, Jian-Qiang;  Jiang, Yang 收藏  |  浏览/下载：1/0  |  提交时间：2019/12/03 Auxiliary models  Blow down  Passive safety systems  Safety analysis  Safety analysis codes  Super-critical pressures  Supercritical water cooled reactors   Evolution of precipitate in nickel-base alloy 718 irradiated with argon ions at elevated temperature 会议论文 作者:  Li, Tiecheng;  Chen, Jihong;  Ma, Shuli;  Luo, Fengfeng;  Jin, Shuoxue 收藏  |  浏览/下载：3/0  |  提交时间：2019/12/05 Precipitation  Superlattice spot  Alloy 718  Ion irradiation  Super-critical water reactors   Evolution of precipitate in nickel-base alloy 718 irradiated with argon ions at elevated temperature 期刊论文 NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 2013, 卷号: 307 作者:  Jin, Shuoxue;  Luo, Fengfeng;  Ma, Shuli;  Chen, Jihong;  Li, Tiecheng 收藏  |  浏览/下载：3/0  |  提交时间：2019/12/05 Precipitation  Superlattice spot  Alloy 718  Ion irradiation  Super-critical water reactors   Structural Characterization of Nickel-Base Alloy C-276 Irradiated with Ar Ions 期刊论文 PLASMA SCIENCE & TECHNOLOGY, 2012, 卷号: 14, 期号: 6 作者:  Jin Shuoxue;  Guo Liping;  Yang Zheng;  Zhou Zhongpo;  Fu Dejun 收藏  |  浏览/下载：5/0  |  提交时间：2019/12/05 irradiation damage  nickel-base alloy  C-276 alloy  super-critical water reactors   Microstructural evolution in nickel alloy C-276 after Ar-ion irradiation at elevated temperature 期刊论文 MATERIALS CHARACTERIZATION, 2012, 卷号: 72 作者:  Jin, Shuoxue;  He, Xinfu;  Li, Tiecheng;  Ma, Shuli;  Tang, Rui 收藏  |  浏览/下载：3/0  |  提交时间：2019/12/05 Irradiation damage  Nickel-base alloy C-276  Multi-scale modeling  Microstructure  Super-critical water reactors   TEM Characterization of Self-ion Irradiation Damage in Nickel-base Alloy C-276 at Elevated Temperature 期刊论文 JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2012, 卷号: 28, 期号: 11 作者:  Jin, Shuoxue;  Guo, Liping;  Ren, Yaoyao;  Tang, Rui;  Qiao, Yanxin 收藏  |  浏览/下载：3/0  |  提交时间：2019/12/05 Irradiation damage  Transmission electron microscopy (TEM)  Nickel-base alloy C-276  Super-critical water reactors   Development of sub-channel analysis code for CANDU-SCWR 期刊论文 2010, 2010 Yu Jiyang; Wang Songtao; Jia Baoshan 收藏  |  浏览/下载：2/0  |  提交时间：2017/06/15 sub-channel  SCWR  CANDU  ASSERT-PV  HEAT-TRANSFER  REACTORS  Nuclear Science & Technology