Modelling one-third field operation in the ITER pre-fusion power operation phase

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Abstract

In the four-stage approach of the new ITER Research Plan, the first pre-fusion power operation (PFPO) phase will only have limited power available from external heating and current drive (H&CD) systems: 20-30 MW provided by the electron cyclotron resonance heating (ECRH) system. Accessing the H-mode confinement regime at such low auxiliary power requires operating at low magnetic field, plasma current and density, i.e. 1.8 T and 5 MA for a density between 40% and 50% of the Greenwald density. II-mode plasmas at 5 MA/1.8 T will also be investigated in the second PFPO phase when ITER will have its full complement of H&CD capabilities installed, i.e. 20-30 MW of ECRH, 20 MW of ion cyclotron resonance heating and 33 MW of neutral beam injection. This paper describes the operational constraints and the II&CD capabilities for such scenarios in hydrogen and helium plasmas, to assess their viability and the issues it will be possible to address with them. The modelling results show that 5 MA/1.8 T scenarios are viable and will allow the exploration of the H-mode physics and control issues foreseen in the ITER Research Programme in the PFPO phases.

Original languageEnglish
Article number126014
Number of pages12
JournalNuclear Fusion
Volume59
Issue number12
DOIs
Publication statusPublished - Dec 2019
MoE publication typeA1 Journal article-refereed

Keywords

  • heating and current drive
  • ITER
  • one-third field operation
  • NBI
  • ICRH
  • ECRH
  • tokamak
  • CURRENT DRIVE
  • TRANSPORT
  • TOKAMAK
  • ABSORPTION
  • CODE

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