Mechanisms of plasma rotation effects on the stability of type-I edge-localized mode in tokamaks

Aiba, N.; Furukawa, Masato; Hirota, Mitsutomo; Oyama, N.; Kojima, A.; Tokuda, S.; Yagi, M.

doi:10.1088/0029-5515/51/7/073012

Cited by 28 publications

(52 citation statements)

References 21 publications

(36 reference statements)

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“…Analysis of ELM stability with extended MHD models in JET, JT-60U and future JT-60SA tokamak plasmas N Aiba 1 , S Pamela 2 , M Honda 3 , H Urano 3 , C Giroud 2 , E Delabie 4 , L Frassinetti 5 , I Lupelli 2 , N Hayashi 3 , G Huijsmans 6,7 , the JET Contributors 8 and JT-60SA Research Unit 9…”

Section: Plasma Physics and Controlled Fusionmentioning

confidence: 99%

“…Therefore, it is necessary to develop operation scenarios and/or control techniques in order to avoid such large ELM heat loads. The important presupposition required to achieve this objective is the precise prediction of the plasma conditions triggering the ELM, and many past works have shown that a stability analysis with the ideal MHD model has successfully explained the plasma conditions observed in the experiments [1][2][3]. These results proved that the type-I ELM is triggered by an ideal MHD mode, called a peelingballooning mode (PBM), and the trigger condition is determined by the amount of plasma pressure and current density near the edge transport barrier region (pedestal).…”

Section: Introductionmentioning

confidence: 99%

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Analysis of ELM stability with extended MHD models in JET, JT-60U and future JT-60SA tokamak plasmas

Aiba

Pamela

Honda

et al. 2017

Plasma Phys. Control. Fusion

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Section: Plasma Physics and Controlled Fusionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Analysis of ELM stability with extended MHD models in JET, JT-60U and future JT-60SA tokamak plasmas

Aiba

Pamela

Honda

et al. 2017

Plasma Phys. Control. Fusion

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“…33,36 The effect on the stability of peeling modes is negligible. 36 In JT60U, analysis of the pedestal stability 37 showed that the pedestal is well below the MHD stability limit when the (counter) toroidal rotation was neglected. In this case, the counter toroidal rotation was found to have a significant destabilising effect on the most unstable modes.…”

Section: A Linear Mhd Stability Limitsmentioning

confidence: 99%

Modelling of edge localised modes and edge localised mode control

et al. 2015

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Edge Localised Modes (ELMs) in ITER Q ¼ 10 H-mode plasmas are likely to lead to large transient heat loads to the divertor. To avoid an ELM induced reduction of the divertor lifetime, the large ELM energy losses need to be controlled. In ITER, ELM control is foreseen using magnetic field perturbations created by in-vessel coils and the injection of small D2 pellets. ITER plasmas are characterised by low collisionality at a high density (high fraction of the Greenwald density limit). These parameters cannot simultaneously be achieved in current experiments. Therefore, the extrapolation of the ELM properties and the requirements for ELM control in ITER relies on the development of validated physics models and numerical simulations. In this paper, we describe the modelling of ELMs and ELM control methods in ITER. The aim of this paper is not a complete review on the subject of ELM and ELM control modelling but rather to describe the current status and discuss open issues. [

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“…If the electrostatic potential is a flux function, equations (5), (6) and (7) can be simply combined to obtain a variant of equation (16) accounting for arbitrary poloidal density variations. This would be the case if the impurity concentration is small and the inertial effects are negligible for the main ions.…”

Section: Theoretical Background and Measurement Principlementioning

confidence: 99%

Indirect measurement of poloidal rotation using inboard–outboard asymmetry of toroidal rotation and comparison with neoclassical predictions

et al. 2013

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An alternative experimental spectroscopic measurement of poloidal plasma rotation in toroidally confined plasmas is proven effective in the TCV tokamak. Charge exchange recombination measurements of the toroidal rotation profile over the full mid-plane plasma diameter are used to infer the complete bi-dimensional flow structure of the intrinsic C 6+ impurity, which includes its poloidal component. For divergence free flows, the difference between the toroidal rotation frequency f t = u t /R at the inboard and outboard locations on the same flux surface is proportional to the poloidal rotation. This indirect measurement provides increased accuracy as the measured quantity f t,in − f t,out ≈ 4qu p /R axis (q is the local safety factor) is larger than the intrinsic uncertainties of a direct spectroscopic measurement of poloidal velocity. The method is applied in a variety of TCV ohmic and electron cyclotron heated L-mode plasmas in the banana-plateau collisionality regime (0.2 < ν * ii < 2.4). In the radial range of normalized poloidal flux ρ ψ < 0.8, an impurity poloidal velocity of u p = 0.5-2.5 km s −1 is observed, always in the electron diamagnetic drift direction. The measurements are compared with neoclassical calculations and they agree in magnitude and sign to within <1 km s −1 .

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Mechanisms of plasma rotation effects on the stability of type-I edge-localized mode in tokamaks

Cited by 28 publications

References 21 publications

Analysis of ELM stability with extended MHD models in JET, JT-60U and future JT-60SA tokamak plasmas

Analysis of ELM stability with extended MHD models in JET, JT-60U and future JT-60SA tokamak plasmas

Modelling of edge localised modes and edge localised mode control

Indirect measurement of poloidal rotation using inboard–outboard asymmetry of toroidal rotation and comparison with neoclassical predictions

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