Numerically derived parametrisation of optimal RMP coil phase as a guide to experiments on ASDEX Upgrade. (13th January 2017)

• Record Type: Journal Article
• Authors: Ryan, D A; Liu, Y Q; Li, L; Kirk, A; Dunne, M; Dudson, B; Piovesan, P; Suttrop, W; Willensdorfer, M
• Other Names: collab.; collab.
• Is Part Of: Plasma physics and controlled fusion. Volume 59:Number 2(2017:Feb.)
• Publication Date: 2017-01-13
• Subjects: ELM mitigation -- RMP coils -- plasma response -- RMP coil phase -- ASDEX Upgrade -- MARS-F; Plasma (Ionized gases) -- Periodicals; Controlled fusion -- Periodicals; 530.44
• DOI: 10.1088/1361-6587/59/2/024005
• Languages: English
• ISSNs: 0741-3335

Abstract

Abstract: Edge localised modes (ELMs) are a repetitive MHD instability, which may be mitigated or suppressed by the application of resonant magnetic perturbations (RMPs). In tokamaks which have an upper and lower set of RMP coils, the applied spectrum of the RMPs can be tuned for optimal ELM control, by introducing a toroidal phase difference Δ Φ between the upper and lower rows. The magnitude of the outermost resonant component of the RMP field ∣ b res 1 ∣ (other proposed criteria are discussed herein) has been shown experimentally to correlate with mitigated ELM frequency, and to be controllable by Δ Φ (Kirk et al 2013 Plasma Phys. Control. Fusion 53 043007 ). This suggests that ELM mitigation may be optimised by choosing Δ Φ = Δ Φ opt, such that ∣ b res 1 ∣ is maximised. However it is currently impractical to compute Δ Φ opt in advance of experiments. This motivates this computational study of the dependence of the optimal coil phase difference Δ Φ opt, on global plasma parameters β N and q 95, in order to produce a simple parametrisation of Δ Φ opt . In this work, a set of tokamak equilibria spanning a wide range of ( β N, q 95 ) is produced, based on a reference equilibrium from an ASDEX Upgrade experiment. The MARS-F code (Liu et al 2000 Phys. Plasmas 7 3681 ) is then used to compute Δ Φ opt across this equilibrium set for toroidal mode numbers n = 1–4, both for the vacuum field and including the plasma response. The computational scan finds that for fixed plasma boundary shape, rotation profiles and toroidal mode number n, Δ Φ opt is a smoothly varying function of ( β N, q 95 ). A 2D quadratic function in ( β N, q 95 ) is used to parametrise Δ Φ opt, such that for given ( β N, q 95 ) and n, an estimate of Δ Φ opt may be made without requiring a plasma response computation. To quantify the uncertainty of the parametrisation relative to a plasma response computation, Δ Φ opt is also computed using MARS-F for a set of benchmarking points. Each benchmarking point consists of a distinct free boundary equilibrium reconstructed from an ASDEX Upgrade RMP experiment, and set of experimental kinetic profiles and coil currents. Comparing the MARS-F predictions of Δ Φ opt for these benchmarking points to predictions of the 2D quadratic, shows that relative to a plasma response computation with MARS-F the 2D quadratic is accurate to 26.5° for n = 1, and 20.6° for n = 2. Potential sources for uncertainty are assessed.