Zobrazeno 1 - 10
of 211
pro vyhledávání: '"Xiao, Bingjia"'
Autor:
Maris, Andrew, Rea, Cristina, Pau, Alessandro, Hu, Wenhui, Xiao, Bingjia, Granetz, Robert, Marmar, Earl, team, the EUROfusion Tokamak Exploitation, team, the Alcator C-Mod, team, the ASDEX Upgrade, team, the DIII-D, team, the EAST, team, the TCV
The "density limit" is one of the fundamental bounds on tokamak operating space, and is commonly estimated via the empirical Greenwald scaling. This limit has garnered renewed interest in recent years as it has become clear that ITER and many tokamak
Externí odkaz:
http://arxiv.org/abs/2406.18442
Autor:
Ai, Xinkun, Zheng, Wei, Zhang, Ming, Chen, Dalong, Shen, Chengshuo, Guo, Bihao, Xiao, Bingjia, Zhong, Yu, Wang, Nengchao, Yang, Zhoujun, Chen, Zhipeng, Chen, Zhongyong, Ding, Yonghua, Pan, Yuan, team, J-TEXT
Publikováno v:
Nuclear Engineering and Technology 2023
The full understanding of plasma disruption in tokamaks is currently lacking, and data-driven methods are extensively used for disruption prediction. However, most existing data-driven disruption predictors employ supervised learning techniques, whic
Externí odkaz:
http://arxiv.org/abs/2303.14965
Autor:
Zheng, Wei, Xue, Fengming, Zhang, Ming, Chen, Zhongyong, Shen, Chengshuo, Ai, Xinkun, Wang, Nengchao, Chen, Dalong, Guo, Bihao, Ding, Yonghua, Chen, Zhipeng, Yang, Zhoujun, Shen, Biao, Xiao, Bingjia, Pan, Yuan
Predicting disruptions across different tokamaks is a great obstacle to overcome. Future tokamaks can hardly tolerate disruptions at high performance discharge. Few disruption discharges at high performance can hardly compose an abundant training set
Externí odkaz:
http://arxiv.org/abs/2208.09594
Publikováno v:
In Fusion Engineering and Design June 2024 203
Accurate plasma shape control is the basis of tokamak plasma experiments and physical research. Modeling of the linearized control response of plasma shape and position has been widely used for shape controller design in the last several years. But i
Externí odkaz:
http://arxiv.org/abs/2011.00238
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.
EAST (Experimental Advanced Superconducting Tokamak) Technical Diagnostic System (TDS) is used to monitor the outlet temperature of all superconducting coils, in case of temperature anomaly, it will trigger safety interlock system to meet EAST device
Externí odkaz:
http://arxiv.org/abs/1806.10663
Autor:
Song, Yuntao, Li, Jiangang, Wan, Yuanxi, Liu, Yong, Wang, Xiaolin, Wan, Baonian, Fu, Peng, Weng, Peide, Wu, Songtao, Duan, Xuru, Yang, Qingwei, Feng, Kaiming, Li, Qiang, Ye, Mingyou, Zhuang, Ge, Liang, Yunfeng, Gao, Xiang, Chen, Changan, Wang, Heyi, Zheng, Guoyao, Xu, Yuhong, Qian, Tianlin, Chan, Vincent, Xiao, Bingjia, Lu, Kun, Zheng, Jinxing, Lu, Mingxuan, Liu, Dequan, Liu, Jian, Wu, Yu, Liu, Xufeng, Shi, Yi, Hou, Binglin, Liu, Chen, Ge, Jian, Zhou, Caipin, Ran, Hong, Wang, Qijie, Wang, Xiaoyu, Liu, Songlin, Liu, Sumei, Yao, Damao, Cheng, Yong, Hu, Liqun, Hu, Chundong, Liu, Fukun, Chen, Gen
Publikováno v:
In Fusion Engineering and Design October 2022 183
Autor:
Wang, Hao, Yuan, Qiping, Hu, Wenhui, Xiao, Bingjia, Ji, Zhenshan, Zhang, Ruirui, Zhang, Shuguang
Publikováno v:
In Fusion Engineering and Design September 2022 182
Autor:
Zheng, Wei, Gan, Rui, Yuan, Qiping, Guo, Heru, Ma, Hengben, Zhang, Ming, Xiao, Bingjia, Pan, Yuan
Publikováno v:
In Fusion Engineering and Design September 2022 182