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Title: E × B flow driven electron temperature bifurcation in a closed slot divertor with ion B × ∇B away from the X-point in the DIII-D tokamak

Journal Article · · Nuclear Fusion
ORCiD logo [1]; ORCiD logo [1];  [2]; ORCiD logo [1]; ORCiD logo [3];  [4]; ORCiD logo [5]; ORCiD logo [6]; ORCiD logo [1];  [1]; ORCiD logo [7];  [1];  [8]
  1. General Atomics, San Diego, CA (United States)
  2. ENN Group, Hebei (China)
  3. Oak Ridge Associated Univ., Oak Ridge, TN (United States)
  4. Zap Energy Inc., Seattle, WA (United States)
  5. Univ. of Tennessee, Knoxville, TN (United States)
  6. Univ. of Toronto, ON (Canada)
  7. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  8. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

An electron temperature bifurcation is observed in the small angle slot divertor, which has been developed to enhance neutral cooling across the divertor target by coupling a closed slot structure with appropriate target shaping. Experiments in the DIII-D tokamak and associated SOLPS-ITER modeling with full drifts find a strong interplay between drifts and divertor geometry on divertor dissipation. The coupling of divertor geometry and drift flows can strongly affect the path towards divertor detachment onset as the plasma density is raised. With the strike point on the inner slanted surface and ion B × ∇B away from the magnetic X-point, bifurcative transitions were observed with sharp decrease of T e towards detachment onset both experimentally and computationally. This differs from the situation for the open divertor where the Te cliff was only observed for ion B × ∇B towards the X-point. SOLPS-ITER modeling with full drifts demonstrates that the magnitude of the E × B drift flow is comparable with the main plasma flow. The reversal of both the poloidal and radial E × B flows near the strike point leads to rapid density accumulation right near the separatrix, which results in bifurcative step transition of divertor conditions with cold plasma across the entire divertor target plate. These results indicate that the interplay between geometry and drifts should be fully taken into account in future fusion reactor divertor designs.

Research Organization:
General Atomics, San Diego, CA (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Grant/Contract Number:
FC02-04ER54698; SC0019256; AC05-00OR22725; NA0003525
OSTI ID:
1895602
Alternate ID(s):
OSTI ID: 1898977
Journal Information:
Nuclear Fusion, Vol. 62, Issue 12; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

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