Fast and accurate methods of plasma boundary determination in ITER from external magnetic measurements

Kuznetsov, Yu.K.; Kilovataya, T.G.; Yasin, I.V.

doi:10.1016/s0920-3796(96)00573-x

Cited by 2 publications

(4 citation statements)

References 7 publications

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“…A comparison of different reconstruction methods with respect to the plasma shape accuracy has been performed for ITER [23] comprising artificial neural networks, function parameterisation and EFIT. Dedicated fast algorithms for plasma shape determination are reported for tokamaks based on a filament representation of the plasma current, in particular for plasma control and stabilization [336], but also EFIT [337] has been used for shape control at DIII-D [338]. The development of JET plasma shape control system and equilibrium reconstruction, using XLOC, XSC, EQUINOX and EFIT, is reported in [22].…”

Section: Automated Analysismentioning

confidence: 99%

Diagnostics for steady state plasmas

Hartfuß¹,

König²,

Werner³

2006

Plasma Phys. Control. Fusion

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Problems related to the development of diagnostics for steady state fusion plasma experiments are being discussed. The paper concentrates on those necessities already appearing in nowadays non-burning plasma fusion experiments when extending pulse lengths beyond 10 s, i.e. thermal load, erosion, deposition, and long-time signal integration in magnetic diagnostics. Problems arising from high power ECRH under conditions of incomplete absorption are outlined. Individual standard diagnostic systems are discussed to identify their specific problems as well as the opportunities connected with long pulse operation. Burning plasma experiments characterized by intense n-and g-radiation are briefly reviewed for reasons of completeness, dealing with radiation induced processes in windows, fibres, cables, and mirrors. Methods of data handling, real time monitoring, and plasma control are outlined. Index

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Section: Automated Analysismentioning

confidence: 99%

Diagnostics for steady state plasmas

Hartfuß¹,

König²,

Werner³

2006

Plasma Phys. Control. Fusion

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“…The method was first published in Ref. [5] and then investigated by other authors (see, for example, Refs [6][7][8][9][10]). In the work [5], semi-arbitrary filament positions were used.…”

Section: Introductionmentioning

confidence: 99%

“…In the work [5], semi-arbitrary filament positions were used. However, numerical simulations show that optimization of the positions of the filaments is necessary [9,10] to obtain the high model accuracy required for ITER, and optimization of the model flexibility is also important when measurement errors are taken into account. The application of the CF method for the present ITER magnetic configuration was presented briefly in Ref.…”

Section: Introductionmentioning

confidence: 99%

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Plasma boundary determination in ITER by the optimized current filament method

et al. 1998

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An accurate and simple technique for plasma boundary determination in a tokamak from external magnetic measurements is described. The method uses the filamentary current model of the plasma current profile, optimized to comply with the requirement of 1 cm accuracy in the determination of the plasma boundary in ITER. An error analysis is performed by numerical simulation of the ITER plasma configuration. The conclusion is that the method can provide this accuracy provided that the level of relative measurement errors can be kept below 1%.

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Fast and accurate methods of plasma boundary determination in ITER from external magnetic measurements

Cited by 2 publications

References 7 publications

Diagnostics for steady state plasmas

Diagnostics for steady state plasmas

Plasma boundary determination in ITER by the optimized current filament method

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