Initial TCV operation with a baffled divertor

TCV team, EUROfusion MST1 Team

Research output: Contribution to journalArticleAcademicpeer-review

14 Citations (Scopus)

Abstract

The Tokamak à Configuration Variable (TCV) tokamak is in the midst of an upgrade to further its capability to investigate conventional and alternative divertor configurations. To that end, modular and removable gas baffles have been installed to decrease the coupling between the divertor and the plasma core. The baffles primarily seek to suppress the transit of recycling neutrals to closed flux surfaces. A first experimental campaign with the gas baffles has shown that the baffled divertor remains compatible with a wide range of configurations including snowflake and super-X divertors. Plasma density ramp experiments reveal an increase of the neutral pressure in the divertor by up to a factor ×5 compared to the unbaffled divertor and thereby qualitatively confirm simulations with the SOLPS-ITER code that were used to guide the baffle design. Together with a range of new and upgraded divertor diagnostics, the baffled TCV divertor is now used to validate divertor models for ITER and next step devices with particular emphasis on geometric variations.

Original languageEnglish
Article number024002
JournalNuclear Fusion
Volume61
Issue number2
DOIs
Publication statusPublished - Feb 2021

Bibliographical note

Funding Information:
This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training program 2014–2018 and 2019–2020 under Grant Agreement No. 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. This work was supported in part by the Swiss National Science Foundation and the US Department of Energy under Award Number DE-SC0010529.

Keywords

  • Divertor
  • Plasma exhaust
  • TCV tokamak

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