Plasma Control Requirements and Concepts for ITER

Wesley, J.C.; Bartels, H. W.; Boucher, D.; Costley, A.E.; Kock, L. de; Gribov, Y.; Huguet, M.; Janeschitz, G.; Mondino, P.L.; Mukhovatov, V.; Portone, A.; Sugihara, M.; Yonekawa, I.

doi:10.13182/fst97-a19902

Cited by 21 publications

(19 citation statements)

References 4 publications

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“…Minor disruptions which are modelled as producing a drop of up to 20% in ¬ Ô · Ð ¾, generally occur at a frequency of once in every 5 seconds of operation [13], and hence can be considered as isolated step perturbations from control point of view as the plasma position is expected to recover fully before a fresh perturbation arrives. Such large drops in ¬ Ô · Ð ¾ can produce a radial shift of about 3 cm for SST1 plasma as shown in figure 6 and active feedback control can restore the plasma radius to 90± of nominal value within 50 msec which is well within the safety limits of SST1.…”

Section: Case 2: Radial Perturbations Due To Minor Disruptionsmentioning

confidence: 99%

Plasma position control in SST1 tokamak

Bandyopadhyay

Deshpande

2000

Pramana - J Phys

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For long duration steady state operation of SST1, it would be very crucial to maintain the plasma radial and vertical positions accurately. For designing the position controller in SST1 we have adopted the simple linear RZIP control model. While the vertical position instability is slowed down by a set of passive stabilizers placed closed to the plasma edge, a pair of in-vessel active feedback coils can adequately control vertical position perturbations of up to 1 cm. The shifts in radial position arising due to minor disruptions would be controlled by a separate pair of poloidal field (PF) coils also placed inside the vessel, however the controller would ignore fast but insignificant changes in radius arising due to edge localised modes. The parameters of both vertical and radial position control coils and their power supplies are determined based on the RZIP simulations.

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Section: Case 2: Radial Perturbations Due To Minor Disruptionsmentioning

confidence: 99%

Plasma position control in SST1 tokamak

Bandyopadhyay

Deshpande

2000

Pramana - J Phys

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“…is essentially independent of the magnetic control, such as the plasma current, plasma position, and plasma shape, a burn control algorithm can be discussed separately from these controls. 26 On this basis, the plasma core burn control algorithm was proposed using the external heating power from the H-mode power threshold to keep the H-mode and fueling to keep the fusion power at the desired value. 19,20 This control algorithm to keep such quantities has been confirmed to work well for the case of a sudden change in the plasma parameters, such as a sudden change in the confinement factor, alpha ash confinement time, sudden injection of impurities and ab-sorbed fuels, sudden increase in the alpha-particle loss, etc.…”

Section: Power Failure Of the Machine During Burn Operationmentioning

confidence: 99%

“…Recently, burn control diagnostic systems have been proposed based on examination of various control algorithms by authors for a fusion reactor, including ITER, 19,20 which is developed independently of the ITER team. [21][22][23][24][25][26] Based on this work, it is possible to see how the ignited operation behaves after the diagnostic failure. To meet the part of the TAC-12 request and consider the diagnostic failure effect on ignition in a future reactor, we tackle these issues using the method developed for ignition burn control.…”

Section: Introductionmentioning

confidence: 99%

Analyses of Diagnostic Failure Effect and Fail-Safe Ignited Operation in a Tokamak Fusion Reactor

Mitarai

Muraoka

1999

Fusion Technology

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The consequence of the failure effect of burn control diagnostic systems, such as neutron diagnostics, bolometers, electron cyclotron emission power loss diagnostics, interferometer, and lost alpha detector, on ignited operation has been analyzed, and the fail-safe operation in a tokamak fusion reactor including the International Thermonuclear Experimental Reactor (ITER) has been considered. Because the failure of the neutron diagnostic system for fusion power measurement leads to a fusion power surge for the simple control algorithm, the fail-safe control algorithm has been introduced to avoid this problem. As failure of the power loss measurement such as the bolometer system terminates the ignition, then it is less problematic. The effect of the interferometer fringe counting error on the ignited operation is not simple, as just mentioned, and a lost alpha detector can be removed from the feedback system using the preset value.

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“…A set of lower hybrid wave (LHW) system based on modulated LHW control of MHD for HT-7 also produced good result of curbing MHD and avoid or alleviate large split [3][4][5][6]. Passive and active means have been tried and researched on main Tokamak device around the world, such as DIII-D, JET, NSTX, JT-60U, HEP-EP, and generated encouraging achievements [7][8][9][10]. But how to detect and control MHD real-timely with high speed has yet to be studied.…”

Section: Introductionmentioning

confidence: 99%

Design and Implementation of Magneto Hydrodynamics Control System on HT-7 Tokamak

Shu

Luo

Wang

2012

2012 Fourth International Conference on Computational and Information Sciences

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The instability of Magneto Hydrodynamics (MHD) in tokamak plasma is a main factor in deciding high performance operation of the tokamak device. Experimental and theoretical results have shown that plasma rotation can contribute to the stability of MHD. This paper presents a HT-7 MHD active control system using biased voltage electrode based on the MHD signal. Biased voltage produces drift and thus changes rotation of border plasma, while the biased voltage itself can be controlled and changed by intelligent control algorithm, and they can work together to realize MHD active control. This paper details the general architecture and implementation of the control system, which has been successfully adopted in HT-7 experiment in the spring of 2011 and generated useful information.

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Plasma Control Requirements and Concepts for ITER

Cited by 21 publications

References 4 publications

Plasma position control in SST1 tokamak

Plasma position control in SST1 tokamak

Analyses of Diagnostic Failure Effect and Fail-Safe Ignited Operation in a Tokamak Fusion Reactor

Design and Implementation of Magneto Hydrodynamics Control System on HT-7 Tokamak

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