4.5 Article

Power exhaust in the snowflake divertor for L- and H-mode TCV tokamak plasmas

Journal

NUCLEAR FUSION
Volume 54, Issue 2, Pages -

Publisher

IOP PUBLISHING LTD
DOI: 10.1088/0029-5515/54/2/023009

Keywords

magnetic confinement fusion; divertor; snowflake; plasma-material interactions; transport processes in plasma

Funding

  1. Swiss National Science Foundation

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The snowflake (SF) divertor is a plasma configuration that may enable tokamak operation at high performance and lower peak heat loads on the plasma-facing components than a standard single-null divertor. This paper reports on the results of experiments performed on the TCV tokamak in both the low- and high-confinement regimes, wherein the divertor configuration was continuously varied between a standard single-null and a 'SF-plus', which features auxiliary strike points (SPs) in the private flux region of the primary separatrix. The measured edge properties show that, in L-mode, the fraction of the exhaust power reaching the additional SPs is small. During edge-localized modes, up to similar to 20% of the exhausted energy is redistributed to the additional SPs even at an x-point separation of 0.6 times the plasma minor radius, thereby reducing the peak heat flux to the inner primary SP by a factor of 2-3. The observed behaviour is qualitatively consistent with a proposed model for enhanced cross-field transport through the SF's relatively large region of low poloidal field by instability-driven convection.

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