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Title: Modelling of edge localised modes and edge localised mode control

Edge Localised Modes (ELMs) in ITER Q = 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.
Authors:
;  [1] ;  [2] ;  [3] ;  [4] ;  [5] ;  [6] ;  [7]
  1. ITER Organization, Route de Vinon sur Verdon, 13067 Saint Paul Lez Durance (France)
  2. Princeton Plasma Physics Laboratory, Princeton University, Princeton, New Jersey 08543 (United States)
  3. General Atomics, P.O. Box 85608, San Diego, California 92186-5608 (United States)
  4. Laboratory for Nuclear Science, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139-4307 (United States)
  5. Institute for Fusion Studies, University of Texas at Austin, Austin, Texas 78712 (United States)
  6. Lawrence Livermore National Laboratory, Livermore, California 94551 (United States)
  7. Ecole Centrale de Lyon, 69130 Écully, Lyon (France)
Publication Date:
OSTI Identifier:
22408050
Resource Type:
Journal Article
Resource Relation:
Journal Name: Physics of Plasmas; Journal Volume: 22; Journal Issue: 2; Other Information: (c) 2015 U.S. Government; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; COMPUTERIZED SIMULATION; CONTROL; DEUTERIUM; DISTURBANCES; DIVERTORS; EDGE LOCALIZED MODES; ENERGY LOSSES; EXTRAPOLATION; FUEL PELLETS; HEATING LOAD; H-MODE PLASMA CONFINEMENT; ITER TOKAMAK; MAGNETIC FIELDS; PLASMA; SERVICE LIFE