Current drive and current profile control studies in the Tokamak Physics Experiment (TPX)

1996 ◽  
Author(s):  
P. T. Bonoli ◽  
M. Porkolab ◽  
L. Sugiyama ◽  
C. Kessel
1994 ◽  
Author(s):  
M. Porkolab ◽  
P. T. Bonoli ◽  
J. J. Ramos ◽  
M. E. Fenstermacher

2015 ◽  
Vol 2015 ◽  
pp. 1-8 ◽  
Author(s):  
Izaskun Garrido ◽  
Aitor J. Garrido ◽  
Jesús A. Romero ◽  
Edorta Carrascal ◽  
Goretti Sevillano-Berasategui ◽  
...  

One of the main problems of fusion energy is to achieve longer pulse duration by avoiding the premature reaction decay due to plasma instabilities. The control of the plasma inductance arises as an essential tool for the successful operation of tokamak fusion reactors in order to overcome stability issues as well as the new challenges specific to advanced scenarios operation. In this sense, given that advanced tokamaks will suffer from limited power available from noninductive current drive actuators, the transformer primary coil could assist in reducing the power requirements of the noninductive current drive sources needed for current profile control. Therefore, tokamak operation may benefit from advanced control laws beyond the traditionally used PID schemes by reducing instabilities while guaranteeing the tokamak integrity. In this paper, a novel model predictive control (MPC) scheme has been developed and successfully employed to optimize both current and internal inductance of the plasma, which influences the L-H transition timing, the density peaking, and pedestal pressure. Results show that the internal inductance and current profiles can be adequately controlled while maintaining the minimal control action required in tokamak operation.


2001 ◽  
Vol 8 (5) ◽  
pp. 2199-2207 ◽  
Author(s):  
O. Sauter ◽  
C. Angioni ◽  
S. Coda ◽  
P. Gomez ◽  
T. P. Goodman ◽  
...  

2019 ◽  
Vol 203 ◽  
pp. 02008 ◽  
Author(s):  
R.I. Pinsker ◽  
X. Chen ◽  
J.M. Lohr ◽  
C.P. Moeller ◽  
M. Porkolab ◽  
...  

The establishment of reactor-relevant radiofrequency heating and current drive techniques is a focus of work on DIII-D in the next five-year period. This paper gives an overview of the planned experimental work in the areas of (1) nearly vertically launched ECCD, (2) ‘helicon’ (whistlers or fast waves in the lower hybrid range of frequencies) current drive, and (3) high-field-side-launch (HFS) lower hybrid (slow wave) current drive. Each of these techniques addresses the need for efficient off-axis current drive for a steady-state tokamak reactor to supplement the bootstrap current and to provide current profile control, and each will be experimentally assessed at a coupled power level of ~1 MW on DIII-D in the next few years.


1992 ◽  
Author(s):  
David A. Ehst ◽  
Donald L. Pearlstein

2000 ◽  
Vol 40 (3Y) ◽  
pp. 453-459 ◽  
Author(s):  
M Sakamoto ◽  
S Itoh ◽  
K.N Sato ◽  
K Nakamura ◽  
H Zushi ◽  
...  

1990 ◽  
Vol 30 (4) ◽  
pp. 771-775 ◽  
Author(s):  
R. Yoshino ◽  
K. Ushigusa ◽  
T. Imai ◽  
H. Shirai ◽  
K. Shimizu

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