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HFCAS OpenIR

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Deuterium plasma-driven permeation through vanadium, niobium and tantalum membranes 期刊论文
FUSION ENGINEERING AND DESIGN, 2021, 卷号: 172
作者:  Wang, Lu;  Zhou, Hai-Shan;  Liu, Hao-Dong;  Xu, Yu-Ping;  Qi, Qiang;  Luo, Guang-Nan
收藏  |  浏览/下载：84/0  |  提交时间：2021/11/29
Hydrogen isotope separation  Plasma-driven permeation  Super-permeation  Vanadium  Tantalum  Niobium  
Development of a system level code for tritium transport analysis of the WCCB blanket for CFETR 期刊论文
FUSION ENGINEERING AND DESIGN, 2020, 卷号: 153
作者:  Huang, Kai;  Zhao, Xueli;  Ma, Xuebin;  Liu, Songlin
收藏  |  浏览/下载：50/0  |  提交时间：2020/11/26
Tritium transport  System level  WCCB blanket  CFETR  
Effect of deuterium on bonding quality of W/Ti/Steel HIP joints in first wall application 期刊论文
FUSION ENGINEERING AND DESIGN, 2019, 卷号: 138, 期号: 无, 页码: 313-320
作者:  Wang, Ji-Chao;  Huang, Jianjun;  Sun, Huibin;  Gao, Xiang;  Wang, Wanjing;  Li, Qiang;  Xie, Chunyi;  Wang, Xingli;  Chen, Zhen;  Gao, Qingran;  Liu, Songlin;  Luo, Guang-Nan;  Li, Jiangang
浏览  |  Adobe PDF(3970Kb)  |  收藏  |  浏览/下载：77/44  |  提交时间：2020/05/21
W steel  H isotope  Diffusion bonding  CFETR  WCCB  
Modeling of fuel retention in the upper tungsten divertor of EAST from attached to detached divertor plasma 期刊论文
FUSION ENGINEERING AND DESIGN, 2018, 卷号: 136, 页码: 908-913
作者:  Sang, Chaofeng;  Wang, Zhenhou;  Wang, Liang;  Ding, Rui;  Wang, Qi;  Sun, Jizhong;  Wang, Dezhen
收藏  |  浏览/下载：42/0  |  提交时间：2019/12/25
Retention  Divertor  Tungsten  Modeling  
Measurement of velocity and reliability of 50 Hz pellet injector for EAST 期刊论文
FUSION ENGINEERING AND DESIGN, 2018, 卷号: 130, 期号: 无, 页码: 69-75
作者:  Hou, Jilei;  Chen, Yue;  Vinyar, Igor;  Yuan, Xiaolin;  Hu, Jiansheng
浏览  |  Adobe PDF(2420Kb)  |  收藏  |  浏览/下载：60/26  |  提交时间：2019/08/23
Pellet injector  Velocity  Reliability  PI-50  EAST  
A system dynamics model for tritium cycle of pulsed fusion reactor 期刊论文
FUSION ENGINEERING AND DESIGN, 2017, 卷号: 118, 期号: 无, 页码: 5-10
作者:  Zhu, Zuolong;  Nie, Baojie;  Chen, Dehong
浏览  |  Adobe PDF(1855Kb)  |  收藏  |  浏览/下载：69/36  |  提交时间：2018/07/27
Tritium  Tas  Fuel Cycle  Fusion Reactor  System Dynamics  
Development and integration of a 50 Hz pellet injection system for the Experimental Advanced Superconducting Tokamak (EAST) 期刊论文
FUSION ENGINEERING AND DESIGN, 2017, 卷号: 114, 期号: 无, 页码: 40-46
作者:  Yao, Xingjia;  Chen, Yue;  Hu, Jiansheng;  Vinyar, Igor;  Lukin, Alexander;  Yuan, Xiaoling;  Li, Changzheng;  Liu, Haiqing
浏览  |  Adobe PDF(2750Kb)  |  收藏  |  浏览/下载：95/55  |  提交时间：2018/05/02
50 Hz  Pellet Injection  Pumping System Design  Engineering Test  East  
Preliminary RAMI analysis of DFLL TBS for ITER 期刊论文
FUSION ENGINEERING AND DESIGN, 2016, 卷号: 112, 期号: 无, 页码: 192-197
作者:  Wang, Dagui;  Yuan, Run;  Wang, Jiaqun;  Wang, Fang;  Wang, Jin
浏览  |  Adobe PDF(870Kb)  |  收藏  |  浏览/下载：92/49  |  提交时间：2017/12/18
Iter  Dfll Tbm  Rami  Reliability  Availability  
Equivalent determination of tritium production in liquid blanket of fusion reactor using lithium isotopic abundance analysis 期刊论文
FUSION ENGINEERING AND DESIGN, 2016, 卷号: 112, 期号: 无, 页码: 89-92
作者:  Mei Huaping;  Wu Qingsheng;  Chen Jianwei;  Zhang Baoren;  Liu Yuejing
浏览  |  Adobe PDF(492Kb)  |  收藏  |  浏览/下载：90/44  |  提交时间：2017/12/18
Fusion Reactor  Liquid Blanket  Tritium  Lithium Isotope Abundance