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CORC

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Corrosion resistance of 316 stainless steel in a simulated pressurized water reactor improved by laser cladding with chromium 期刊论文
Surface and Coatings Technology, 2022, 卷号: 441
作者:  Gu, Yufen;  Xu, Youwei;  Shi, Yu;  Feng, Changgen;  Volodymyr, Korzhyk
收藏  |  浏览/下载：42/0  |  提交时间：2022/06/20
Fishtail Divertor and its basis surface thermal load bearing performance 期刊论文
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 180
作者:  Li, Yilong;  Zhou, Tong
收藏  |  浏览/下载：2/0  |  提交时间：2022/12/23
In situ measurements of low energy D plasma-driven permeation through He pre-damaged W 期刊论文
NUCLEAR FUSION, 2022, 卷号: 62
作者:  Li, Xue-Chun;  Zhou, Hai-Shan;  Liu, Hao-Dong;  Wang, Lu;  Luo, Guang-Nan
收藏  |  浏览/下载：24/0  |  提交时间：2022/05/05
Decomposition and estimation of the pulsed active power of the CPSS in the CFETR tokamak reactor based on the FFT and improved Prony methods 期刊论文
ENERGY REPORTS, 2022, 卷号: 8
作者:  Hua, Yuting;  Fu, Peng;  Huang, Liansheng;  Li, Shenghu
收藏  |  浏览/下载：50/0  |  提交时间：2022/01/25
Systematic design of snake arm maintainer in nuclear industry 期刊论文
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 176
作者:  Qin, Guodong;  Cheng, Yong;  Pan, Hongtao;  Zhao, Wenlong;  Shi, Shanshuang
收藏  |  浏览/下载：17/0  |  提交时间：2022/05/16
Numerical simulation on the eddy current electromagnetic forces and the mechanical reliability of ITER in-wall shielding blocks induced by plasma disruption events 期刊论文
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 174
作者:  Feng, Changle;  Huang, Shenghong;  Lu, Kun;  Du, Shuangsong;  Ding, Kaizhong
收藏  |  浏览/下载：19/0  |  提交时间：2022/05/16
Design of Coordination System for Composite Mobile Robot Platform Oriented to Nuclear Fusion Vessel 期刊论文
JOURNAL OF FUSION ENERGY, 2021, 卷号: 40
作者:  Zhang, Qiang;  Song, Bo;  Cai, Bin;  Sun, Yuxiang
收藏  |  浏览/下载：53/0  |  提交时间：2021/11/16
A study on nuclear analysis of the divertor region of the CFETR 期刊论文
PLASMA SCIENCE & TECHNOLOGY, 2021, 卷号: 23
作者:  Saidahmed, Rayyan;  Yao, Damao;  Wu, Qiuran;  Liu, Songlin;  Xu, Tiejun
收藏  |  浏览/下载：25/0  |  提交时间：2021/11/15
Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW 期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2021, 卷号: 49
作者:  Li, Jie;  Zhang, Jie;  Liu, Changle;  Liu, Xiaogang;  Gao, Xiang
收藏  |  浏览/下载：55/0  |  提交时间：2021/11/15
Scoping study of lower hybrid current drive for CFETR 期刊论文
NUCLEAR FUSION, 2021, 卷号: 61
作者:  Wallace, G. M.;  Din, B. J.;  Li, M. H.;  Chen, J.;  Baek, S. G.
收藏  |  浏览/下载：47/0  |  提交时间：2021/11/01

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