Feedback Control Modeling of Plasma Position and Current during Intense Heating in ISX-B

作者: L. A. Charlton , D. W. Swain , G. H. Neilson

DOI: 10.1109/TPS.1979.4317235

关键词:

摘要: The ISX-B tokamak at ORNL is designed to have 1.8 MW (and eventually 3 MW) of neutral beam power injected heat the plasma. This may raise s? plasna over 5 percent in less than 50 ms, if plasma MHD stable. results a numerical simulation feedback control system and poloidal coil supplies necessary resulting noncircular (D-shaped or elliptical) are presented. shown be straightforward, although nonlinear voltage-current dependence assumed supplies. required supplied coils order contain under high heating rates estimated.

参考文章(3)
V.S. Mukhovatov, V.D. Shafranov, Plasma equilibrium in a Tokamak Nuclear Fusion. ,vol. 11, pp. 605- 633 ,(1971) , 10.1088/0029-5515/11/6/005
J. Hugill, A. Gibson, Servo-control of plasma position in Cleo-Tokamak Nuclear Fusion. ,vol. 14, pp. 611- 619 ,(1974) , 10.1088/0029-5515/14/5/002
J.L. Anderson, R.S. Booth, R.J. Colchin, R.V. Miskell, J.M. Bailey, Feedback control for plasma equilibrium in ORMAK Nuclear Fusion. ,vol. 16, pp. 629- 637 ,(1976) , 10.1088/0029-5515/16/4/009