Nuclear Materials and Energy (Oct 2022)

Comparative modeling studies of carbon and tungsten impurity transport in the boundary plasma of EAST with a partially detached divertor condition

  • Guoliang Xu,
  • Hui Wang,
  • Rui Ding,
  • Xiaoju Liu,
  • Hang Si,
  • Dahuan Zhu,
  • Rong Yan,
  • Ran Hai,
  • Hai Xie,
  • Junling Chen

Journal volume & issue
Vol. 33
p. 101259

Abstract

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The source and leakage of both C and W are comparatively studied for a partially detached divertor operation condition on EAST. Based on the EAST experiments, sequential SOLPS-DIVIMP simulations are carried out to study the transport of intrinsic impurities in the boundary plasma. Carbon distribution from the fluid SOLPS simulation is in good agreement with the impurity tracing results from the Monte-Carlo DIVIMP simulation. The impurity leakage processes from the divertor target to the core plasma are quantitatively analyzed and divided into three parts: the prompt redeposition, the divertor screening, and the main SOL screening. Under the partially detached divertor condition, W has a higher prompt redeposition rate and a weaker cross-field transport from the main SOL to the core region than C. However, the strong parallel impurity transport from the divertor region to the main SOL makes the total leakage rate of W two times higher than that of C. The impurity velocity gained from the ion temperature gradient force in both the near-SOL detached region and the far-SOL attached region is evaluated. The relatively higher ion temperature gradient velocity of W in the attached region is the main reason for the higher divertor leakage rate than C, and the strong W source in the far-SOL makes the leakage from the attached region more significant.