Effect of plasma response on the fast ion losses due to ELM control coils in ITER

Varje, J.; Asunta, O.; Cavinato, M.; Gagliardi, Mario; Hirvijoki, Eero; Koskela, T.; Kurki-Suonio, T.; Liu, Yueqiang; Parail, V.; Saibene, G.; Sipilä, S.; Snicker, A.; Särkimäki, Konsta; Äkäslompolo, S.

doi:10.1088/0029-5515/56/4/046014

Cited by 43 publications

(62 citation statements)

References 18 publications

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“…[32]. Some of these response field data have been used for further investigation of the fast ion losses in ITER [5].…”

Section: Plasma Response For Four Iter Scenariosmentioning

confidence: 99%

“…However, as has been recently realized, taking into account the plasma response to the 3D external fields may be crucial. This is useful not only just for understanding the modification (plasma shielding and/or amplification) of the field structure due to the plasma response, but also, and perhaps even more importantly, for providing better guidance of correcting these field errors, for understanding the potential mode locking induced by the low-n components of these fields, and for further investigation of energetic particle losses in the presence of the total 3D field perturbations including the plasma response [5].…”

Section: Introductionmentioning

confidence: 99%

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Modelling of 3D fields due to ferritic inserts and test blanket modules in toroidal geometry at ITER

et al. 2016

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Computations in toroidal geometry are systematically performed for the plasma response to 3D magnetic perturbations, produced by ferritic inserts (FIs) and test blanket modules (TBMs), for four ITER plasma scenarios: the 15MA baseline, the 12.5MA hybrid, the 9MA steady state, and the 7.5MA half-field Helium plasma. Due to broad toroidal spectrum of the FI and TBM fields, the plasma response for all the n=1-6 field components are computed and compared. The plasma response is found to be weak for the high-n (n > 4) components. The response is globally not sensitive to the toroidal plasma flow speed, as long as the latter is not reduced by an order of magnitude. This is essentially due to the strong screening effect occuring at a finite flow as predicted for ITER plasmas. The ITER error field correction coils (EFCC) are used to compensate the n = 1 field errors produced by FIs and TBMs for the baseline scenario, for the purpose of avoiding the mode locking. It is found that the middle row of EFCC, with a suitable toroidal phase for the coil current, can provide the best correction of these field errors, according to various optimization criteria. On the other hand, even without correction, it is predicted that these n = 1 field errors do not cause substantial flow damping for the 15MA baseline scenario.

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“…[32]. Some of these response field data have been used for further investigation of the fast ion losses in ITER [5].…”

Section: Plasma Response For Four Iter Scenariosmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Modelling of 3D fields due to ferritic inserts and test blanket modules in toroidal geometry at ITER

et al. 2016

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“…22,23 Finally, the computed plasma response field can be valuable input data for further studies, such as the (enhanced) energetic particle losses due to 3D RMP fields, and the resulting divertor-wall heat loads. 24 This study has revealed that there are essentially two types of plasma response to the applied RMP fields: One is the so-called core-kink response and the other is the edgepeeling response. 7 The difference is that the plasma displacement is strongly localised near the plasma edge-in the pedestal region-with the edge-peeling type of response and is often associated with a dominant single poloidal harmonics in terms of the radial plasma displacement.…”

Section: Introductionmentioning

confidence: 99%

Comparative investigation of ELM control based on toroidal modelling of plasma response to RMP fields

Liu

Kirk

et al. 2017

Physics of Plasmas

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Extensive modelling efforts of the plasma response to the resonant magnetic perturbation fields, utilized for controlling the edge localized mode (ELM), help to identify the edge-peeling response as a key factor, which correlates to the observed ELM mitigation in several tokamak devices, including MAST, ASDEX Upgrade, EAST, and HL-2A. The recently observed edge safety factor window for ELM mitigation in HL-2A experiments is explained in terms of the edge-peeling response. The computed plasma response, based on toroidal single fluid resistive plasma model with different assumption of toroidal flows, is found generally larger in ELM suppressed cases as compared to that of the ELM mitigated cases, in ASDEX Upgrade and DIII-D. The plasma shaping, in particular, the plasma triangularity, contributes to the enhanced plasma response. But the shaping does not appear to be the sole factor-other factors such as the (higher) pedestal pressure and/or current can also lead to increased edge-peeling response.

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“…ASCOT has recently been applied to extensive studies of fusion α-particle wall loads in various ITER scenarios [91,92] with three-dimensional magnetic background and first wall. The effects of toroidal field ripple, mitigated by ferritic inserts at the toroidal field coils, as well as non-periodic magnetic field perturbations caused by the ferritic test blanket modules and control coils for edge-localized modes were studied.…”

Section: Reconstruction Of Ascot Simulations Based On Grs and Ctsmentioning

confidence: 99%

Alpha-particle velocity-space diagnostic in ITER

et al. 2018

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Effect of plasma response on the fast ion losses due to ELM control coils in ITER

Cited by 43 publications

References 18 publications

Modelling of 3D fields due to ferritic inserts and test blanket modules in toroidal geometry at ITER

Modelling of 3D fields due to ferritic inserts and test blanket modules in toroidal geometry at ITER

Comparative investigation of ELM control based on toroidal modelling of plasma response to RMP fields

Alpha-particle velocity-space diagnostic in ITER

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