Progress toward divertor detachment on TCV within H-mode operating parameters

TCV team, EUROfusion MST1 team

Research output: Contribution to journalArticlepeer-review


Recent experiments on Tokamak à Configuration Variable have made significant progress toward partial detachment of the outer divertor in neutral beam heated H-mode plasmas in conventional and alternative divertor configurations. The heating power required to enter H-mode was measured in a range of divertor configurations. It is found that at the core densities most favourable for H-mode access, the L-H threshold power is largely independent of the poloidal flux expansion and major radius of the outer divertor, and in the snowflake minus configuration. A factor 2 reduction in the outer divertor power load was achieved in ELM-free (using a fuelling and nitrogen seeding) and ELMy (using nitrogen seeding) H-mode plasmas. No significant reduction in the outer divertor particle flux was achieved in the ELM-free scenarios, compared with ∼30% reduction in the most strongly detached ELMy cases. The poloidal flux expansion at the outer divertor was not found to significantly alter the cooling of the divertor in the ELM-free scenarios.

Original languageEnglish
Article number065024
Number of pages19
JournalPlasma Physics and Controlled Fusion
Issue number6
Publication statusPublished - 16 May 2019

Bibliographical note

© 2019 Crown copyright. Reproduced with the permission of the Controller of Her Majesty's Stationery Office


  • divertor
  • divertor detachment
  • plasma physics
  • TCV
  • tokamak

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