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Development of an assistant program for CAD-to-cosRMC modelling 期刊论文
FUSION ENGINEERING AND DESIGN, 2020, 卷号: 157
作者:  Du, Hua;  Luo, Yue-Tong;  Han, Chengcun;  Lu, Lei;  Yan, Yiman
收藏  |  浏览/下载:16/0  |  提交时间:2020/10/26
FreeCAD based Monte Carlo modeling approach for fusion reactor facilities 期刊论文
FUSION ENGINEERING AND DESIGN, 2020, 卷号: 155, 页码: 10
作者:  Li, Jin-Yang;  Gu, Long;  Xu, Hu-Shan;  Dai, Yong;  Zhang, You-Peng
收藏  |  浏览/下载:16/0  |  提交时间:2022/01/18
Operation and shutdown dose rate analysis of CFETR ECRH system 期刊论文
Fusion Engineering and Design, 2020, 卷号: 159
作者:  Peng Lu;  Qiuran Wu;  Liyuan Zhang;  Yu Zheng;  Hua Du
收藏  |  浏览/下载:19/0  |  提交时间:2020/10/23
Development of Gd-Si-O dispersed 316L stainless steel for improving neutron shielding performance 期刊论文
NUCLEAR MATERIALS AND ENERGY, 2020, 卷号: 23
作者:  Yang, Xinyi;  Song, Liangliang;  Chang, Bo;  Yang, Qi;  Mao, Xiaodong
收藏  |  浏览/下载:28/0  |  提交时间:2020/11/30
Shielding analysis for TCP and IVVS bio-shield plugs of ITER 期刊论文
FUSION ENGINEERING AND DESIGN, 2020, 卷号: 153
作者:  Baidoo, I. K.;  Wu, Y.;  Song, J.;  Yu, S.;  Jakhar, S.
收藏  |  浏览/下载:5/0  |  提交时间:2020/11/26
Investigation of neutron source model based on EAST plasma shape 期刊论文
FUSION ENGINEERING AND DESIGN, 2020, 卷号: 153
作者:  Huang, Liangsheng;  Hu, Liqun;  Zhou, Mengjie;  Niu, Luying;  Zhong, Guoqiang
收藏  |  浏览/下载:20/0  |  提交时间:2020/11/26
Preliminary design and analyses of the helium cooled ceramic breeder blanket for CFETR phase II 期刊论文
INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2020
作者:  Cui, Shijie;  Zhang, Dalin;  Lang, Yueheng;  Jiang, Xinyu;  Tian, Wenxi
收藏  |  浏览/下载:20/0  |  提交时间:2020/11/26
Investigation on the Nuclear Heat Deposition of Shielding Blanket for CFETR Phase I 期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2020, 卷号: 48
作者:  Zhang, Jianzhong;  Li, Jie;  Zhang, Jie;  Li, Lei;  Qiu, Yang
收藏  |  浏览/下载:19/0  |  提交时间:2020/11/26
Feasibility of an innovative long-life molten chloride-cooled reactor 期刊论文
NUCLEAR SCIENCE AND TECHNIQUES, 2020, 卷号: 31, 期号: 4, 页码: -
作者:  Lin, M;  Cheng, MS;  Dai, ZM
收藏  |  浏览/下载:6/0  |  提交时间:2021/09/06
FUEL  DAMAGE  
Core and blanket thermal-hydraulic analysis of a molten salt fast reactor based on coupling of OpenMC and OpenFOAM 期刊论文
NUCLEAR SCIENCE AND TECHNIQUES, 2020, 卷号: 31, 期号: 9, 页码: -
作者:  Deng, B;  Cui, Y;  Chen, JG;  He, L;  Xia, SP
收藏  |  浏览/下载:20/0  |  提交时间:2021/09/06


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