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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;  Li, Tao-Sheng
收藏  |  浏览/下载：49/0  |  提交时间：2022/01/10
Lithium heat pipe  Bending effect  Marangoni effect  Capillary limit  Heat Pipe-Segmented Thermoelectric Module Converters (HP-STMC)  
Influence of non-ideal gas characteristics on working fluid properties and thermal cycle of space nuclear power generation system 期刊论文
ENERGY, 2021, 卷号: 222
作者:  Xu, Chi;  Kong, Fanli;  Yu, Dali;  Yu, Jie;  Khan, Muhammad Salman
收藏  |  浏览/下载：66/0  |  提交时间：2021/05/06
CBC  Helium-xenon  Physical property parameters  Non-ideal gas  Space nuclear reactors  
Divertor impurity seeding with a new feedback control scheme for maintaining good core confinement in grassy-ELM H-mode regime with tungsten monoblock divertor in EAST 期刊论文
NUCLEAR FUSION, 2020, 卷号: 60
作者:  Xu, G. S.;  Yuan, Q. P.;  Li, K. D.;  Wang, L.;  Xu, J. C.;  Yang, Q. Q.;  Duan, Y. M.;  Meng, L. Y.;  Yang, Z. S.;  Ding, F.;  Liu, J. B.;  Guo, H. Y.;  Wang, H. Q.;  Eldon, D.;  Tao, Y. Q.;  Wu, K.;  Yan, N.;  Ding, R.;  Wang, Y. F.;  Ye, Y.;  Zhang, L.;  Zhang, T.;  Zang, Q.;  Li, Y. Y.;  Liu, H. Q.;  Jia, G. Z.;  Liu, X. J.;  Si, H.;  Li, E. Z.;  Zeng, L.;  Qian, J. P.;  Lin, S. Y.;  Xu, L. Q.;  Wang, H. H.;  Gong, X. Z.;  Wan, B. N.
浏览  |  Adobe PDF(4069Kb)  |  收藏  |  浏览/下载：663/38  |  提交时间：2020/10/22
divertor impurity seeding  radiative divertor feedback control  partial detachment  grassy-ELM H-mode regime  tokamak  
Tomography of the positive-pitch fast-ion velocity distribution in DIII-D plasmas with Alfven eigenmodes and neoclassical tearing modes 期刊论文
NUCLEAR FUSION, 2020, 卷号: 60
作者:  Madsen, B.;  Salewski, M.;  Heidbrink, W. W.;  Stagner, L.;  Podesta, M.;  Lin, D.;  Garcia, A. V.;  Hansen, P. C.;  Huang, J.
收藏  |  浏览/下载：65/0  |  提交时间：2020/11/26
velocity-space tomography  fast-ion D-alpha spectroscopy  fast ions  Alfven eigenmodes  neoclassical tearing modes  kick model  DIII-D tokamak  
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;  Kun Xu;  Songlin Liu;  Xiaojie Wang;  Jianjun Huang;  Bin Yu
浏览  |  Adobe PDF(7206Kb)  |  收藏  |  浏览/下载：86/33  |  提交时间：2020/10/23
CFETR, ECRH, Operation dose, Shutdown dose, NASCA  
Achieving a robust grassy-ELM operation regime in CFETR 期刊论文
NUCLEAR FUSION, 2020, 卷号: 60
作者:  Zhu, Yi-Ren;  Li, Ze-Yu;  Chan, V. S.;  Chen, Jia-Le;  Jian, Xiang;  Dudson, B. D.;  Garofalo, A. M.;  Snyder, P. B.;  Xu, Xue-Qiao;  Zhuang, G.
收藏  |  浏览/下载：61/0  |  提交时间：2020/11/26
grassy-ELMs  collisionality  high beta(p)  peeling-ballooning mode  CFETR  experimental comparison  
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：68/41  |  提交时间：2020/10/26
fast ion  orbit following Monte Carlo calculation  RMP  resonance  
Heat transfer characteristic analysis of a novel annular nuclear heat exchanger for propulsion system 期刊论文
ANNALS OF NUCLEAR ENERGY, 2019, 卷号: 126, 期号: 无, 页码: 84-94
作者:  Bai, Ying;  Zhao, Zhumin;  Xu, Gang;  Bai, Yunqing
浏览  |  Adobe PDF(3188Kb)  |  收藏  |  浏览/下载：100/24  |  提交时间：2020/05/21
Annular channel  Nuclear thermal propulsion  Enhanced convection heat transfer  Performance optimization  
Summary of the 8th Asia-Pacific Transport Working Group (APTWG) Meeting 期刊论文
NUCLEAR FUSION, 2019, 卷号: 59, 期号: 4, 页码: 14
作者:  Shi, Z. B.;  Cheng, J.;  Xu, Y. H.;  Tokuzawa, T.;  Qiu, Z. Y.;  Sasaki, M.;  Zhong, W. L.;  Ida, K.;  Wang, Z. X.;  Zhang, T.;  Kim, J.;  Kwon, J. M.;  Kobayashi, T.;  Lee, W. C.
浏览  |  Adobe PDF(463Kb)  |  收藏  |  浏览/下载：111/55  |  提交时间：2020/03/31
turbulence  transport  conference  APTWG  plasma  
Stability analysis on flow parameters in coolant temperature control system of lead-cooled fast reactor 期刊论文
ANNALS OF NUCLEAR ENERGY, 2019, 卷号: 126, 期号: 无, 页码: 367-375
作者:  Yao, Yuantao;  Wang, Jianye;  Zhang, Junjun;  Yang, Minghan
浏览  |  Adobe PDF(1997Kb)  |  收藏  |  浏览/下载：132/52  |  提交时间：2020/05/21
Lead-cooled fast reactor  Coolant temperature control system  Coolant flow rate  Stability analysis  Real stability radius