A framework for the design of a plasma current and shape controller in next-generation tokamaks

被引:9
作者
Ariola, M
Pironti, A
Portone, A
机构
[1] Univ Naples Federico II, Dipartimento Informat & Sistemist, Assoc Euratom ENEA CREATE, I-80125 Naples, Italy
[2] ITER Joint Cent Team, Naka, Ibaraki 31101, Japan
来源
FUSION TECHNOLOGY | 1999年 / 36卷 / 03期
关键词
plasma control; ITER; tokamak;
D O I
10.13182/FST99-A107
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The problem of designing a plasma current and shape control system for a tokamak is dealt with, anal a complete framework based on a validated linearized plasma model is developed. Starting from the equilibrium configurations to control and given the required performance, a procedure for choosing the parameters to control is outlined Then, a method is proposed to evaluate the best performance one could ever expect from a control system, given the actual limitations due to the power supply. A procedure for designing a linear controller is described. The use of a modern multivariable technique, such as the H-infinity theory, allows one to take into account the many existing constraints and to find a trade-off among performance, robustness, and control effort. The methodology proposed is general and can be applied in principle to any tokamak plant. The simulation results refer to the International Thermonuclear Experimental Reactor (ITER) tokamak. A controller designed following almost the same steps has been successfully tested on an existing tokamak.
引用
收藏
页码:263 / 277
页数:15
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