CORC

浏览/检索结果: 共36条,第1-10条 帮助

限定条件                
已选(0)清除 条数/页:   排序方式:
Preliminary exploration of a WTaVTiCr high-entropy alloy as a plasma-facing material 期刊论文
NUCLEAR FUSION, 2022, 卷号: 62
作者:  Li, Yu;  Sun, Yuhan;  Cheng, Long;  Yuan, Yue;  Jia, Baohai
收藏  |  浏览/下载:23/0  |  提交时间:2022/12/22
Thermodynamic simulation and structural optimization of the collimator in the drift duct of EAST-NBI 期刊论文
NUCLEAR ENGINEERING AND TECHNOLOGY, 2022, 卷号: 54
作者:  Tang, Ning;  Hu, Chun-dong;  Xie, Yuan-lai;  Wei, Jiang-long;  Cui, Zhi-Wei
收藏  |  浏览/下载:17/0  |  提交时间:2022/12/23
Implementation of CO2 and PbLi as working fluids in RELAP5/MOD3.3 towards accident analysis of COOL blanket for CFETR 期刊论文
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 184
作者:  Wang, Wenjia;  Cheng, Xiaoman;  Yu, Yi;  Wu, Qiuran;  Liu, Songlin
收藏  |  浏览/下载:17/0  |  提交时间:2022/12/23
The Preload Analyses of CFETR CSMC Pre-compression Structure 期刊论文
IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2022, 卷号: 32
作者:  Wang, Xianwei;  Han, Peng;  Xu, Xusong;  Xie, Fei;  Wang, Zhaoliang
收藏  |  浏览/下载:32/0  |  提交时间:2022/05/16
Fatigue life prediction of hypervapotron for CFETR divertor 期刊论文
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 174
作者:  Chen, Xianfeng;  Qin, Shijun;  Wang, Qingfeng;  Cao, Jin
收藏  |  浏览/下载:11/0  |  提交时间:2022/05/16
Performance evaluation of ultra-long lithium heat pipe using an improved lumped parameter model 期刊论文
NUCLEAR SCIENCE AND TECHNIQUES, 2021, 卷号: 32
作者:  Hu, Chong-Ju;  Yu, Da-Li;  He, Mei-Sheng;  Mei, Hua-Ping;  Yu, Jie
收藏  |  浏览/下载:21/0  |  提交时间:2022/01/10
Numerical Analysis of the Convective Heat Transfer Coefficient Enhancement of a Pyro-Breaker Utilized in Superconducting Fusion Facilities 期刊论文
ENERGIES, 2021, 卷号: 14
作者:  He, Jun;  Wang, Ke;  Li, Jiangang
收藏  |  浏览/下载:36/0  |  提交时间:2022/01/10
Thermal analysis of the EAST tokamak 期刊论文
FUSION ENGINEERING AND DESIGN, 2021, 卷号: 168
作者:  Zhang, Ming;  Zhong, Huayong;  Ren, Yong;  Wang, Dongquan;  Gao, Xiang
收藏  |  浏览/下载:12/0  |  提交时间:2021/08/30
Design study and preliminary feasibility analysis of divertor with ITER-Like PFU for advanced tokamak 期刊论文
FUSION ENGINEERING AND DESIGN, 2021, 卷号: 164
作者:  Peng, Xuebing;  Mao, Xin;  Liu, Peng;  Yang, Lei;  Qian, Xinyuan
收藏  |  浏览/下载:42/0  |  提交时间:2021/04/26
Power balance investigation in long-pulse high-performance discharges with ITER-like tungsten divertor on EAST 期刊论文
NUCLEAR FUSION, 2020, 卷号: 60
作者:  Liu, Y. K.;  Gao, X.;  Hanada, K.;  Yu, Y. W.;  Liu, H. Q.
收藏  |  浏览/下载:21/0  |  提交时间:2020/10/21


©版权所有 ©2017 CSpace - Powered by CSpace