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RF plasma simulations using the TOMATOR 1D code: A case study for TCV helium ECRH plasmas

  • T. Wauters*
  • , J. Buermans
  • , R. Haelterman
  • , V. Moiseenko
  • , D. Ricci
  • , T. Verhaeghe
  • , S. Coda
  • , D. Douai
  • , Antti Hakola
  • , A. Lyssoivan
  • , D. Van Eester
  • *Corresponding author for this work
    • École Royale Militaire
    • Kharkiv Institute of Physics and Technology
    • National Research Council (CNR)
    • Ecole Polytechnique Fédérale de Lausanne (EPFL)
    • Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA)

    Research output: Contribution to journalArticleScientificpeer-review

    Abstract

    The 1-dimensional reaction-diffusion-convection code TOMATOR-1D describes plasma production by RF waves inside a tokamak using the Braginskii continuity and heat balance equations. The model simulates self-consistent radial density and temperature profiles for magnetised plasma mixtures of hydrogen and helium. The model reproduces the density profiles of X2 electron cyclotron resonance heating (ECRH) plasmas on TCV and proposes a Bohm-like poloidal magnetic field dependent scaling for anomalous diffusion and a convection scaling that results from drifts in the toroidal magnetic field configuration. A relation is proposed between the anomalous diffusion and the outward convection in toroidal plasmas. It is found that the EC absorption efficiency decreases at higher power, which is understood from the acceleration of electrons beyond the optimal energy for the electron impact ionisation of helium. A dramatic increase of the absorption efficiency is seen at intermediate vertical magnetic field values of Bz = 0.25%â'0.5%BT which results in the highest density plasmas. Losses along the field lines in the vertical direction become dominant at higher fields which effectively reduces the plasma density in these discharges. To arrive at predictive capabilities towards ECRH plasmas on JT-60SA and ITER, the proposed scalings, subsuming dependencies on the torus major radius and the toroidal field strength, need to be validated in a multi-machine study.
    Original languageEnglish
    Article number105010
    Number of pages8
    JournalPlasma Physics and Controlled Fusion
    Volume62
    Issue number10
    DOIs
    Publication statusPublished - 20 Aug 2020
    MoE publication typeA1 Journal article-refereed

    Funding

    This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 and 2019–2020 under grant agreement No 633053. This work was supported in part by the Swiss National Science Foundation.

    UN SDGs

    This output contributes to the following UN Sustainable Development Goals (SDGs)

    1. SDG 7 - Affordable and Clean Energy
      SDG 7 Affordable and Clean Energy

    Keywords

    • ECRH
    • ECWC
    • Plasma start-up
    • TCV
    • Tokamak
    • Wall conditioning

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