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HFCAS OpenIR

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Parametric analysis of influence factors to the in-vacuum vessel LOCA for CFETR based on RELAP5 期刊论文
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 184
作者:  Ling, Qixin;  Wang, Wenjia;  Cheng, Xiaoman;  Liu, Songlin
收藏  |  浏览/下载：39/0  |  提交时间：2022/12/23
CFETR  In-VV LOCA  RELAP5  Pressure increasing rate  Leaked water mass  
Highly underexpanded helium jet and its effect on dust resuspension under in-vessel loss of coolant accident of fusion reactor 期刊论文
NUCLEAR FUSION, 2022, 卷号: 62
作者:  Qin, Zhijie;  Zhang, Shichao;  Wang, Zhen;  Chen, Zhibin;  Li, Taosheng
收藏  |  浏览/下载：34/0  |  提交时间：2022/12/23
in-vessel LOCA  highly underexpanded jet  Mach disk  friction velocity  
Numerical investigation of the core outlet temperature fluctuation for the lead-based reactor 期刊论文
ANNALS OF NUCLEAR ENERGY, 2018, 卷号: 117, 期号: 无, 页码: 194-201
作者:  Wang, Lizhi;  Wu, Guowei;  Wang, Jin;  Jin, Ming;  Song, Yong
浏览  |  Adobe PDF(3527Kb)  |  收藏  |  浏览/下载：74/33  |  提交时间：2019/08/23
Temperature fluctuation  Lead-based reactor  Core outlet  
Thermal-Hydraulic Analysis for One Water-Cooled Blanket Module of CFETR Based on RELAP5 期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1704-1712
作者:  Lin, Shuang;  Cheng, Xiaoman;  Jiang, Kecheng;  Ma, Xuebin;  Liu, Songlin
浏览  |  Adobe PDF(3232Kb)  |  收藏  |  浏览/下载：79/41  |  提交时间：2019/06/04
Accident analysis  loss of coolant accident (LOCA)  RELAP5  water-cooled ceramic breeder blanket (WCCB)  
Preliminary Comparison of Wet Bypass Accident Consequences Between ITER and a Helium-Cooled Fusion Power Plant 期刊论文
FUSION SCIENCE AND TECHNOLOGY, 2018, 卷号: 74, 期号: 3, 页码: 238-245
作者:  Chen, Shanqi;  Ge, Daochuan;  Wang, Zhen;  Jia, Jiangtao;  Chen, Zhibin;  Hu, Liqin
浏览  |  Adobe PDF(1170Kb)  |  收藏  |  浏览/下载：102/53  |  提交时间：2019/12/20
Fusion power plant  helium  ITER  accident  no-public evacuation  
Inverse kinematics research using obstacle avoidance geometry method for EAST Articulated Maintenance Arm (EAMA) 期刊论文
FUSION ENGINEERING AND DESIGN, 2017, 卷号: 119, 期号: 无, 页码: 1-11
作者:  Wang, Kun;  Song, Yuntao;  Wu, Huapeng;  Wei, Xiaoyang;  Khan, Shahab Ud-Din;  Cheng, Yong
浏览  |  Adobe PDF(4803Kb)  |  收藏  |  浏览/下载：85/40  |  提交时间：2018/05/25
Redundant Inverse Kinematics  Otpp  Midfs  Eama  Remote Handing  Redundant Manipulator  
Thermal strain measurement of EAST W/Cu divertor structure using electric resistance strain gauges 期刊论文
FUSION ENGINEERING AND DESIGN, 2016, 卷号: 113, 期号: 无, 页码: 1-5
作者:  Wang, Xingli;  Wang, Wanjing;  Wang, Jichao;  Wei, Ran;  Sun, Zhaoxuan;  Li, Qiang;  Xie, Chunyi;  Chen, Hong-En;  Wang, Kaiqiang;  Wu, Lei;  Chen, Zhenmao;  Luo, Guang-Nan
浏览  |  Adobe PDF(1466Kb)  |  收藏  |  浏览/下载：108/53  |  提交时间：2017/09/07
East  Divertor  Thermal Strain  Strain Gauge  Measurement  
A Possible Shielding Blanket Module for CFETR Reactor 期刊论文
JOURNAL OF FUSION ENERGY, 2016, 卷号: 35, 期号: 2, 页码: 341-345
作者:  Yang, Hao;  Zhang, Jie;  Li, Lei;  Qiu, Yang;  Liu, Changle;  Yao, Damao
Adobe PDF(2141Kb)  |  收藏  |  浏览/下载：111/68  |  提交时间：2017/07/13
Cfetr  Sb Module  Design  Analysis  
Preliminary thermal hydraulic safety analysis of water-cooled ceramic breeder blanket for CFETR 期刊论文
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2016, 卷号: 53, 期号: 11, 页码: 1673-1680
作者:  Cheng, Xiaoman;  Ma, Xuebin;  Chen, Youhua;  Huang, Kai;  Liu, Songlin
浏览  |  Adobe PDF(1461Kb)  |  收藏  |  浏览/下载：88/44  |  提交时间：2017/12/18
Cfetr  Blanket  Thermal Hydraulics  Accident Analysis  Relap5  
Controllability study of EAST plasma vertical instability and improvement in future 期刊论文
Fusion Engineering and Design, 2014, 卷号: 89, 期号: 5, 页码: 563-567
作者:  L. Liu;  B.J. Xiao;  D.A. Humphreys;  Z.P. Luo;  S.L. Chen
Adobe PDF(1429Kb)  |  收藏  |  浏览/下载：60/31  |  提交时间：2015/12/23