Experimental studies of the snowflake divertor in TCV

B. Labit*, G. P. Canal, N. Christen, B. P. Duval, B. Lipschultz, T. Lunt, F. Nespoli, H. Reimerdes, U. Sheikh, C. Theiler, C. K. Tsui, K. Verhaegh, W. A J Vijvers

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review


To address the risk that, in a fusion reactor, the conventional single-null divertor (SND) configuration may not be able to handle the power exhaust, alternative divertor configurations, such as the Snowflake divertor (SFD), are investigated in TCV. The expected benefits of the SFD-minus in terms of power load and peak heat flux are discussed and compared to experimental measurements. In addition, key results obtained during the last years are summarized.

Original languageEnglish
Number of pages6
JournalNuclear Materials and Energy
Early online date27 Mar 2017
Publication statusE-pub ahead of print - 27 Mar 2017

Bibliographical note

© 2017 Published by Elsevier Ltd. This is an author-produced version of the published paper. Uploaded in accordance with the publisher’s self-archiving policy


  • Detachment
  • Heat load mitigation
  • Snowflake divertor
  • Tokamaks

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