Since 18 of December 2019 uses Nucleus credentials. Visit our help pages for information on how to Register and Sign-in using Nucleus.
May 10 – 15, 2021
Virtual Event
Europe/Vienna timezone
The Conference will be held virtually from 10-15 May 2021

Non-linear MHD modelling of Edge Localized Modes suppression by Resonant Magnetic Perturbations in ITER.

May 12, 2021, 8:30 AM
Virtual Event

Virtual Event

Regular Poster Magnetic Fusion Theory and Modelling P3 Posters 3


Marina Becoulet (IRFM/CEA)


The intensive experimental and theoretical study of the Edge Localized Modes (ELMs) and methods of their control is of great importance for ITER [1]. The application of small external Resonant Magnetic Perturbations (RMPs) has been demonstrated to be efficient in ELMs suppression/mitigation in present day tokamaks [2]. RMPs are foreseen as one of the methods of ELMs control in ITER [3]. However, a significant progress in understanding of physics of the interaction of ELMs with RMPs is still required to make reliable predictions for next step machines such as ITER and DEMO. The non-linear MHD code JOREK [4] is successfully used to model ELMs mitigation and suppression in the present day tokamaks. Recent modelling results for RMP experiments in ASDEX-Upgrade [5] and KSTAR [6] validated in many aspects the RMPs and ELMs physics models implemented in JOREK code [7]. It was demonstrated in particular that non-linear multi-harmonics approach, realistic tokamak geometry with the X-point and the Scrape-Off-Layer (SOL), realistic geometry and spectrum of RMP coils, toroidal rotation, the bi-fluid diamagnetic effects and neoclassical poloidal friction represent a minimum model which permits to reproduce experimental results.
In the present work the non-linear MHD modelling results of ELM mitigation and suppression by RMPs in ITER are presented for the first time. The realistic ITER geometry including divertor, SOL was used. The parameters of the standard H-mode scenario at 15MA/5.3T modelled by ASTRA code [8] with toroidal flow profiles self-consistently calculated with NBI heating and momentum input documented in ITER IMAS database (short=13102, run=4) were used as initial conditions. The ITER baseline design which includes 27 ELM control coils with three toroidal rows, located at the low field side (LFS) as described in detail in ITER IMAS machine description database (shot=1180, run=17) was used for vacuum modelling with optimized spectrum for main toroidal symmetry n=3 [9-10]. The vacuum RMP boundary conditions were imposed on the computational boundary of the JOREK code similar to [5-7], then the rotating plasma response and interaction of RMPs with ELMs in the core and pedestal plasma were modelled.
For the first time, ELMs suppression by RMPs was demonstrated in multi-harmonics modeling for ITER taking into account main toroidal harmonics n=3 and n=6 in RMP coils spectrum. The threshold for ELM suppression was found to be about ~60kAt maximum of the current amplitude over all RMP coils versus of capability of 90 kAt. In the ELM suppressed state, previously unstable modes without RMPs, responsible for ELM crash, are stable and only non-linearly driven modes coupled to the imposed (here n=3 and n=6) harmonics of RMPs are triggered and reach saturated state with RMPs, producing continuous turbulent transport at the edge consequently reducing pressure gradient. The 3D divertor magnetic footprints, heat and particle fluxes in stationary RMP phase are characterized.

Acknowledgements: This work has been supported by EUROFUSION CfP-WP19-ENR-01/MPG-03, IO/CT/18/430000. This work benefited from HPC resources from CINECA Marconi-Fusion (project FUA33_JOREK3DE).
Disclaimer. The views and opinions expressed herein do not necessarily reflect those of the European Commission. ITER is the Nuclear Facility INB no. 174. The views and opinions expressed herein do not necessarily reflect those of the ITER Organization.

[1] A Loarte A. et al Plasma Phys. Control. Fusion 45(2003)1549
[2] M Fenstermacher et al Phys of Plas15(2008)56122
[3] R Hawryluk et al. Nucl. Fus 49(2009) 065012
[4] G T A Huysmans et al Plasma Phys Control Fusion 51 (2009) 124012
[5] F Orain et al Phys. Plasmas 26(2019), 042503
[6] S K Kim et al Nucl. Fusion 60(2020), 026009
[7] F Orain et al Phys of Plasmas 20(2013)102510
[8] A.R. Polevoi et al Nucl. Fusion 45 (2005)1451
[9] T Evans et al Nucl. Fusion 53 (2013) 093029
[10] L Li et al Plasma Phys. Control. Fusion 59 (2017) 044005

Country or International Organization France
Affiliation CEA/IRFM

Primary author


Dr Alberto Loarte (ITER Organization) Dr Alexei POLEVOI (ITER Organization) Prof. Guido Huijsmans (CEA,IRFM) Dr Shimpei Futatani (Department of Physics, Universitat Politècnica de Catalunya (UPC), Barcelona) Dr Simon Pinches (ITER Organization)

Presentation materials