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浏览/检索结果: 共17条，第1-10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 Analysis of the drop dynamics of control rod assembly in a LBE-cooled research reactor 期刊论文 ANNALS OF NUCLEAR ENERGY, 2020, 卷号: 149 作者:  Arthur, Emmanuel Maurice;  Zhang, Chaodong;  Debrah, Seth Kofi;  Yamoah, Stephen;  Wang, Lei 收藏  |  浏览/下载：50/0  |  提交时间：2020/12/07 Lead-cooled fast reactor  Lead-bismuth eutectic  Control rod assembly  Drop time  Hydraulic resistance   Progress in extending high poloidal beta scenarios on DIII-D towards a steady-state fusion reactor and impact of energetic particles 期刊论文 NUCLEAR FUSION, 2020, 卷号: 60 作者:  Huang, J.;  Garofalo, A. M.;  Qian, J. P.;  Gong, X. Z.;  Ding, S. Y. 收藏  |  浏览/下载：38/0  |  提交时间：2020/11/30 tokamak  steady state  high bootstrap current  energetic particle   Corrosion Behaviors and Mechanisms of ODS Steel Exposed to Static Pb-Bi Eutectic at 600 and 700 degrees C 期刊论文 ACTA METALLURGICA SINICA, 2020, 卷号: 56, 期号: 10, 页码: 1366-1376 作者:  Bao Feiyang;  Li Yanfen;  Wang Guangquan;  Zhang Jiarong;  Yan Wei 收藏  |  浏览/下载：51/0  |  提交时间：2021/02/02 advanced nuclear energy system  Pb-Bi eutectic (LBE)  oxide dispersion strengthened (ODS) steel  high temperature corrosion  oxide scale   Corrosion Behaviors and Mechanisms of ODS Steel Exposed to Static Pb-Bi Eutectic at 600 and 700 degrees C 期刊论文 ACTA METALLURGICA SINICA, 2020, 卷号: 56, 期号: 10, 页码: 1366-1376 作者:  Bao Feiyang;  Li Yanfen;  Wang Guangquan;  Zhang Jiarong;  Yan Wei 收藏  |  浏览/下载：57/0  |  提交时间：2021/02/02 advanced nuclear energy system  Pb-Bi eutectic (LBE)  oxide dispersion strengthened (ODS) steel  high temperature corrosion  oxide scale   A new integrated SSCs safety classification method and a case study on CN HCCB TES 期刊论文 ANNALS OF NUCLEAR ENERGY, 2020, 卷号: 145 作者:  Sun, Ming;  Wang, Jin;  Wang, Fang;  Yu, Jie;  Yin, Yuan 收藏  |  浏览/下载：17/0  |  提交时间：2020/10/29 SSCs  Safety classification  Fault tree analysis  Importance  CN HCCB TES   Effect of Dilution Ratio of the First 309L Cladding Layer on the Microstructure and Mechanical Properties of Weld Joint of Connecting Pipe-Nozzle to Safe-End in Nuclear Power Plant 期刊论文 ACTA METALLURGICA SINICA, 2020, 卷号: 56, 期号: 8, 页码: 1057-1066 作者:  Zhang Maolong;  Lu Yanhong;  Chen Shenghu;  Rong Lijian;  Lu Hao 收藏  |  浏览/下载：18/0  |  提交时间：2021/02/02 buttering welding  dilution ratio  microstructure  mechanical property  cracking mechanism   Stationary high-performance grassy ELM regime in EAST 期刊论文 NUCLEAR FUSION, 2020, 卷号: 60 作者:  Yang, Q. Q.;  Xu, G. S.;  Yan, N.;  Wang, Y. F.;  Lin, X. 收藏  |  浏览/下载：17/0  |  提交时间：2020/10/26 grassy ELM regime  EAST tokamak  CFETR   Preliminary design and analysis on the cogeneration system for Small Modular Lead-cooled Fast Reactor 期刊论文 APPLIED THERMAL ENGINEERING, 2020, 卷号: 174 作者:  Xu, Chi;  Li, Yang;  Jin, Ming;  Kong, Fanli;  Gao, Sheng 收藏  |  浏览/下载：23/0  |  提交时间：2020/11/26 SMLFR  Cogeneration system  Thermodynamic analysis  GEN-IV reactors   Multi-coupled commutation analysis in EAST poloidal field quench protection circuits based on fuse model 期刊论文 FUSION ENGINEERING AND DESIGN, 2020, 卷号: 155 作者:  Deng, Tianbai;  Gao, Ge;  Fu, Peng;  Huang, Liansheng;  Song, Zhiquan 收藏  |  浏览/下载：68/0  |  提交时间：2020/11/26 Fuse model  Arc model  Quench protection  Multi-coupled coils  Poloidal field   Tritium safety and confinement loop design of tritium plant in a FPP 期刊论文 FUSION ENGINEERING AND DESIGN, 2020, 卷号: 154 作者:  Wei, Shiping;  Wang, Haixia;  Jia, Jiangtao;  Chen, Zhibin;  Jiang, Jieqiong 收藏  |  浏览/下载：31/0  |  提交时间：2020/11/26 FPP  Tritium plant  Tritium inventory  Tritium safety  Tritium confinement