Towards steady-state operational design for the data and PF control systems of the HT-7U

被引:10
作者
Luo, JR [1 ]
Zhu, L [1 ]
Wang, HZ [1 ]
Ji, ZS [1 ]
Wang, F [1 ]
机构
[1] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China
关键词
D O I
10.1088/0029-5515/43/9/310
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
Fusion energy is an ultimate and inexhaustible source of energy for mankind and is expected to be obtained in controlled operation within this century. Among various possible candidates for fusion, the tokamak is presently the most qualified one, and since it uses superconducting magnetic coils, it will be adequate for steady-state operation. The HT-7U superconducting tokamak is a part of national project in China on fusion research, scheduled to become available on-line by the end of 2004 (Wan Y.X and HT-7 & HT-7U Groups 2000 Overview of steady state operation of HT-7 and present status of the HT-7U project Nucl. Fusion 40 1057). The control system of the HT-7U is designed as a distributed control system (HT7UDCS), including many subsystems that provide the various functions of supervision, remote control, real-time monitoring, data acquisition and data handling. The major features of the HT-7U tokamak, which make long-pulse (similar to1000 s) operation possible are the flexible poloidal field (PF) system, an auxiliary heating system, the current-driving system and a divertor system. In order to realize these features simultaneously, real-time data handling and analysis, along with a significant control capability is required. This paper discusses the design of the HT7UDCS.
引用
收藏
页码:862 / 869
页数:8
相关论文
共 17 条
[1]  
FERRON JR, 1997, GAA22637
[2]   Tore supra data acquisition: A system for long duration discharges [J].
Guillerminet, B ;
Le Luyer, M ;
Rothan, B .
FUSION ENGINEERING AND DESIGN, 1999, 43 (3-4) :259-264
[3]   The acquisition system for Tore Supra 1000 s discharges [J].
Guillerminet, B ;
How, J .
FUSION ENGINEERING AND DESIGN, 2000, 48 (1-2) :155-161
[4]  
HEIMANN P, 2002, P 3 IAEA TCM STEAD S
[5]   Recent progress on high performance steady state plasmas in the superconducting tokamak TRIAM-1M [J].
Itoh, S ;
Sato, KN ;
Nakamura, K ;
Zushi, H ;
Sakamoto, M ;
Hanada, K ;
Jotaki, E ;
Makino, K ;
Kawasaki, S ;
Nakashima, H ;
Yoshida, N .
NUCLEAR FUSION, 1999, 39 (9Y) :1257-1270
[6]   CONTINUOUS MONITORING AND DATA-ACQUISITION SYSTEM FOR STEADY-STATE TOKAMAK OPERATION [J].
JOTAKI, E ;
ITOH, S .
FUSION TECHNOLOGY, 1995, 27 (02) :171-175
[7]   The evolution of control and data acquisition at JET [J].
Krom, JG .
FUSION ENGINEERING AND DESIGN, 1999, 43 (3-4) :265-273
[8]   Lower hybrid current drive experiments and improved performance on the HT-7 superconducting tokamak [J].
Kuang, GL ;
Liu, YX ;
Shan, JF ;
Xu, WH ;
Zhang, XQ ;
Liu, DC ;
Liu, FK ;
Zhu, YB ;
Zhang, C ;
Zheng, GH ;
Wu, JS ;
Lin, JN ;
Ding, BJ ;
Xu, HD ;
Fang, YD ;
Li, JG ;
Luo, JR ;
Zhang, XD ;
Wan, BN ;
Zhao, QC ;
Mao, JS ;
Gao, X ;
Zhang, SY ;
Li, CF ;
Gu, XM ;
Qing, PJ ;
Fan, HY ;
Liu, SX ;
Ling, BL ;
Ding, BL ;
Li, YH ;
Wu, ZW ;
Jie, YX ;
Liu, S ;
Xie, JK ;
Wan, YX .
NUCLEAR FUSION, 1999, 39 (11Y) :1769-1774
[9]   EQUILIBRIUM-ANALYSIS OF CURRENT PROFILES IN TOKAMAKS [J].
LAO, LL ;
FERRON, JR ;
GROEBNER, RJ ;
HOWL, W ;
STJOHN, H ;
STRAIT, EJ ;
TAYLOR, TS .
NUCLEAR FUSION, 1990, 30 (06) :1035-1049
[10]   ICRF boronization - A new technique towards high efficiency wall coating for superconducting tokamak reactors [J].
Li, JG ;
Zhao, YP ;
Gu, XM ;
Li, CF ;
Wan, BN ;
Zhang, XD ;
Luo, JR ;
Gong, XZ ;
Xie, JE ;
Wan, YX ;
Qin, PJ ;
Wang, XM ;
Meng, YD ;
Li, SF ;
Gao, X ;
Yang, Y ;
Xue, DY ;
Mao, YZ ;
Den, X ;
Chen, L ;
Fang, YC ;
Yin, FX ;
Liu, SX ;
Yang, XK ;
Xu, DZ ;
Ding, JY ;
Jie, YX ;
Zhao, QC ;
Mao, JS ;
Zhang, SY ;
Zhao, JY ;
Hu, JS ;
Fan, HY ;
Wei, MS ;
Lin, BL ;
Wang, GX ;
De Fang, Y ;
Shen, WC .
NUCLEAR FUSION, 1999, 39 (08) :973-977