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

Research output: Contribution to journalArticleScientificpeer-review

Researchers

Research units

  • ITER Org
  • IRFM-CEA
  • NRC Kurchatov Inst, National Research Centre - Kurchatov Institute
  • Max Planck Inst Plasma Phys, Max Planck Society
  • TEC Partner, EUROfus Consortium Member, LPP ERM KMS
  • CNR, Istituto Fisica del Plasma "Piero Caldirola" (IFP-CNR), Consiglio Nazionale delle Ricerche (CNR), Ist Fis Plasma
  • Joint Stock Company DV Efremov Inst Electrophys A
  • Culham Sci Ctr, Culham Science Centre, CCFE

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.

Details

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

    Research areas

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

ID: 37833758