Diamagnetic loop for the first plasma in the KSTAR machine

Bak, J. G.; Lee, S. G.; Ka, E. M.

doi:10.1063/1.2956963

Cited by 8 publications

(5 citation statements)

References 8 publications

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“…Similar double-loop configurations have been in use in the tokamaks Tore Supra [11], KSTAR [16,19], HL-2A [21], J-TEXT [26], WEST [27] and stellarators Heliotron J [9], U-2M and U-3M [22].…”

mentioning

confidence: 93%

“…The standard approach to this task is to arrange supplementary measurements allowing the evaluation of B e . These can be done with either so-called compensation coils [2, 3, 10, 12-15, 17-21, 23-25, 27-29] by-passing the plasma and reacting on t B e ¶ ¶ / only, or a second diamagnetic loop [2,9,11,16,19,21,22,26,27] d2 covering a different area compared to the other one d1.…”

Section: Introductionmentioning

confidence: 99%

“…The larger one will be mounted on the interior surface of the vacuum vessel (on-wall loop d1), similar to that once exploited and then removed in DIII-D [14], now in operation in the KSTAR [16,19], and planned for the use in the ITER tokamak [3].…”

mentioning

confidence: 99%

“…In the KSTAR, the accurate position measurement of the loop pair inside the vacuum vessel has been done by using a laser tracker system after the installation [16,19]. Nevertheless, the flux pl dF could not be properly evaluated from the double-loop measurements, and one reason was a small S S 1…”

mentioning

confidence: 99%

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Diamagnetic diagnostics of rapid events in the T-15MD tokamak

Dubrov

Pustovitov

2019

Plasma Phys. Control. Fusion

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The resistive wall effect on the diamagnetic signal is analysed. The calculations are performed by the DINA code for the T-15MD tokamak. The accompanying analytics reveals the main dependencies allowing easy extrapolation of the results to any other tokamak. It is explicitly shown that the key parameter in the task is the decay time of the poloidal current induced in the wall. This current can be neglected for the events with transient times longer by factor of ten. If the plasma evolves faster, the difference between the measured signal and the plasma-produced variation of the toroidal magnetic flux will be larger than 10%, up to 100% for typically rapid thermal quenches. Incorporation of the induction equation for the wall current greatly improves the diagnostic capabilities.

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mentioning

confidence: 93%

Section: Introductionmentioning

confidence: 99%

mentioning

confidence: 99%

mentioning

confidence: 99%

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Diamagnetic diagnostics of rapid events in the T-15MD tokamak

Dubrov

Pustovitov

2019

Plasma Phys. Control. Fusion

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“…The plasma-stored energy (W dia ) is measured by a diamagnetic loop. 22 Other diagnostic systems are shown in Fig. 1(a).…”

Section: Introductionmentioning

confidence: 99%

Edge localized mode characteristics during edge localized mode mitigation by supersonic molecular beam injection in Korea Superconducting Tokamak Advanced Research

et al. 2015

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It has been reported that supersonic molecular beam injection (SMBI) is an effective means of edge localized mode (ELM) mitigation. This paper newly reports the changes in the ELM, plasma profiles, and fluctuation characteristics during ELM mitigation by SMBI in Korea Superconducting Tokamak Advanced Research. During the mitigated ELM phase, the ELM frequency increased by a factor of 2–3 and the ELM size, which was estimated from the Dα amplitude, the fractional changes in the plasma-stored energy and the line-averaged electron density, and divertor heat flux during an ELM burst, decreased by a factor of 0.34–0.43. Reductions in the electron and ion temperatures rather than in the electron density were observed during the mitigated ELM phase. In the natural ELM phase, frequency chirping of the plasma fluctuations was observed before the ELM bursts; however, the ELM bursts occurred without changes in the plasma fluctuation frequency in the mitigated ELM phase.

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