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Exploring the engineering limit of heat flux of a W/RAFM divertor target for fusion reactors 期刊论文
NUCLEAR FUSION, 2018, 卷号: 58, 期号: 6, 页码: 13
作者:  Mao, X.;  Fursdon, M.;  Chang, X. B.;  Zhang, J. W.;  Liu, P.;  Ellwood, G.;  Qian, X. Y.;  Qin, S. J.;  Peng, X. B.;  Barrett, T. R.;  Liu, P.
浏览  |  Adobe PDF(2584Kb)  |  收藏  |  浏览/下载：100/54  |  提交时间：2019/06/03
reactor divertor  plasma facing unit  heat transfer coefficient  thermo-mechanical stress  fatigue life  Bree diagram  
Conceptual design study for CFETR divertor target using CLAM steel as structural material 期刊论文
FUSION ENGINEERING AND DESIGN, 2018, 卷号: 131, 页码: 90-95
作者:  Liu, Peng;  Song, Yuntao;  Peng, Xuebing;  Qin, Shijun;  Mao, Xin;  Qian, Xinyuan;  Zhang, Jianwu
收藏  |  浏览/下载：44/0  |  提交时间：2019/11/12
Divertor  CLAM steel  CFETR Monoblock  Assessment rules  Irradiation  
RAMI Analysis for PFCs of EAST Divertor 期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1406-1411
作者:  Zhang, Yang;  Qin, Shijun;  Cao, Lei;  Yao, Damao;  Li, Jiangang
浏览  |  Adobe PDF(2252Kb)  |  收藏  |  浏览/下载：83/41  |  提交时间：2019/08/23
Divertor  experimental advanced superconducting tokamak (EAST)  plasma-facing components (PFCs)  reliability  availability  maintainability  and inspectability (RAMI)