中文版 | English

在结果中检索

HFCAS OpenIR

浏览/检索结果: 共35条，第1-10条 帮助

限定条件    
已选(0)清除 条数/页：   排序方式：
Parametric study of helicon wave current drive in CFETR 期刊论文
NUCLEAR FUSION, 2023, 卷号: 63
作者:  Wu, Xianshu;  Li, Jingchun;  Chen, Jiale;  Xu, Guosheng;  Dong, Jiaqi;  Wang, Zhanhui;  Sun, Aiping;  Zhong, Wulv
收藏  |  浏览/下载：15/0  |  提交时间：2023/11/10
wave heating  current drive  radio frequency  helicon  fast wave  lower hybrid wave  
Status of the WEST travelling wave array antenna design and results from the high power mock-up 期刊论文
NUCLEAR FUSION, 2022, 卷号: 62
作者:  Ragona, R.;  Durodie, F.;  Messiaen, A.;  Ongena, J.;  Van Schoor, M.;  Agzaf, S.;  Batal, T.;  Bernard, J-M;  Courtois, X.;  Delaplanche, J-M;  Dumont, R.;  Durand, F.;  Faisse, F.;  Firdaouss, M.;  Gargiulo, L.;  Garibaldi, P.;  Hillairet, J.;  Hoang, T.;  Lombard, G.;  Mollard, P.;  Chen, Z.;  Song, Y.;  Xu, H.;  Yang, Q.;  Yu, C.
收藏  |  浏览/下载：72/0  |  提交时间：2022/02/14
travelling wave  ICRH  combline  WEST  DEMO  
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.;  Bondi, P. T.;  Shiraiwai, S.;  Liu, L.;  Wu, C. B.
收藏  |  浏览/下载：53/0  |  提交时间：2021/11/01
lower hybrid current drive  china fusion engineering test reactor  non-inductive current drive  steady state tokamak  
Experimental study on tritium breeding in water-cooled ceramic breeder blanket mock-up under D-T neutron irradiation conditions 期刊论文
NUCLEAR FUSION, 2021, 卷号: 61
作者:  Zhu, Qingjun;  Chen, Wuhui;  Bao, Jie;  Du, Hua;  Liu, Songlin;  Huang, Kai
收藏  |  浏览/下载：60/0  |  提交时间：2021/06/15
D–  T neutrons  blanket mock-up  neutronics experiments  WCCB blanket  CFETR  
Interface design of the blanket system for CFETR 期刊论文
NUCLEAR FUSION, 2020, 卷号: 60
作者:  Lei, Mingzhun;  Song, Yuntao;  Ni, Xiaojun;  Wu, Xinghua;  Shen, Junsong;  Liu, Sumei;  Liu, Songlin;  Wang, Xiaoyu;  Cheng, Yong;  Xie, Yuanlai;  Wang, Xiaojie;  Liu, Liang;  Chen, Gen;  Xu, Tiejun;  Lu, Kun
收藏  |  浏览/下载：67/0  |  提交时间：2020/11/30
CFETR  interface design  blanket system  integration  
The performance of first CORC cable solenoid insert for development of CFETR high-field magnet 期刊论文
NUCLEAR FUSION, 2020, 卷号: 60
作者:  Jin, H.;  Qin, J. G.;  Zhou, C.;  Liu, H. J.;  Liu, F.;  Gao, P.;  Xiao, G. Y.;  Ma, H. J.;  Li, J. G.;  Wu, Y.;  Jiang, D. H.;  Wu, K. H.;  Ma, T.;  Tan, Y. F.;  Li, J. J.
浏览  |  Adobe PDF(1491Kb)  |  收藏  |  浏览/下载：83/45  |  提交时间：2020/10/26
ReBCO coated conductor  high field magnet  EM and thermal cycles  current carrying performance  
Effects of triangularity on the fusion performance of CFETR 期刊论文
NUCLEAR FUSION, 2020, 卷号: 60
作者:  Zhou, Cheng-Xi;  Chen, Jia-Le;  Chan, V. S.;  Jian, Xiang;  Zhuang, G.;  Zhu, Yi-Ren
收藏  |  浏览/下载：29/0  |  提交时间：2020/10/26
triangularity  turbulence  collisionality  reversed magnetic shear  thermo-diffusion  CFETR  integrated modeling  
Burning fraction, radial transport, and steady state profiles of multi-species particles in CFETR burning plasmas 期刊论文
NUCLEAR FUSION, 2020, 卷号: 60
作者:  Lin, W. S.;  Wang, X. G.;  Xiao, C. J.;  Wang, Z. H.;  Kong, D. F.;  Lang, Y.
收藏  |  浏览/下载：33/0  |  提交时间：2020/11/26
CFETR  D-T fusion plasma  tritium burning fraction  
Progress in the conceptual design of the CFETR toroidal field coil with rectangular conductors 期刊论文
NUCLEAR FUSION, 2020, 卷号: 60
作者:  Liu, Xiaogang;  Wu, Fan;  Wang, Zhaoliang;  Li, Guoqiang;  Liu, Xiaoju;  Li, Hang;  Li, Junjun;  Ren, Yong;  Wu, Yu;  Gao, Xiang
收藏  |  浏览/下载：57/0  |  提交时间：2020/11/26
tokamak  DEMO  superconducting magnet  TF  cable-in-conduit conductor  electromagnetic load  mechanical analysis  
Resonant effects on the loss of energetic trapped ions induced by low-n resonant magnetic perturbations 期刊论文
NUCLEAR FUSION, 2019
作者:  He, K.;  Wan, B. N.;  Sun, Y.;  Jia, M.;  Shi, T.;  Wang, H. H.;  Zhang, X. J.
浏览  |  Adobe PDF(13289Kb)  |  收藏  |  浏览/下载：71/42  |  提交时间：2020/10/26
fast ion  orbit following Monte Carlo calculation  RMP  resonance