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
Publication date
August 2017
DOI Publisher
Elsevier BV Journal
Nuclear Materials and EnergyAbstract
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. Keywords: Tokamaks, Snowflake divertor, Detachment, Heat load mitigatio
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