Plasma and Fusion Research

Volume 16, 2403004 (2021)

Regular Articles

Simulation of Impurity Transport and Deposition in the Closed Helical Divertor in the Large Helical Device
Mamoru SHOJI1), Gakushi KAWAMURA1,2), Juri ROMAZANOV3), Andreas KIRSCHNER3), Alina EKSAEVA3), Dmitry BORODIN3), Suguru MASUZAKI1,2) and Sebastijan BREZINSEK3)
1)
National Institute for Fusion Science, National Institutes of Natural Sciences, 322-6 Oroshi-cho, Toki 509-5292, Japan
2)
The Graduate University for Advanced Studies, SOKENDAI, Shonan Village, Hayama 240-0913, Japan
3)
Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung - Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), Jülich 52425, Germany
(Received 16 November 2020 / Accepted 14 December 2020 / Published 10 February 2021)

Abstract

Long pulse discharges in the Large Helical Device have often been interrupted by large amounts of dust particle emission from the divertor region caused by the exfoliation of carbon-rich mixed material deposition layers. The plasma wall interaction code ERO2.0 has provided the simulation results of the three-dimensional distribution of the carbon flux density in the divertor region which is quite reasonable with the observed distribution of the carbon-rich deposition layers. The code has also succeeded in reproducing the reduction of the carbon deposition layers on dome plates by changing the target plate configuration in the divertor region. The ERO2.0 simulations have also successfully explained dust particle emission from the inboard side near the equatorial plane for the new target plate configuration at the termination of a long pulse discharge. These simulation results prove that the ERO2.0 code is applicable to predicting the possible position from where the dust particles are released, and to designing an optimized divertor configuration for performing stable long pulse discharges with controlled dust particle emission.

Keywords

ero2.0, plasma wall interaction, simulation, impurity transport, divertor, peripheral plasma, emc3-eirene, large helical device

DOI: 10.1585/pfr.16.2403004

Full Text

PDF format (3.3Mbytes) PDF Download

References

  • [1] Y. Takeiri et al., Nucl. Fusion 57, 102023 (2017).
  • [2] M. Shoji et al., J. Nucl. Mater. 415, S557 (2011).
  • [3] S. Masuzaki et al., Plasma Fusion Res. 6, 1202007 (2011).
  • [4] M. Shoji et al., Nucl. Fusion 55, 053014 (2015).
  • [5] M. Tokitani et al., J. Nucl. Mater. 463, 91 (2015).
  • [6] J. Romazanov et al., Nucl. Mater. Energy 18, 331 (2019).
  • [7] Y. Feng et al., Plasma Phys. Control. Fusion 44, 611 (2002).
  • [8] G. Kawamura et al., Contrib. Plasma Phys. 54, 437 (2014).
  • [9] G. Kawamura et al., Plasma Phys. Control. Fusion 60, 084005 (2018).
  • [10] The ADAS User Manual (version 2.6) http://adas.phys.strath.ac.uk/ (2004).
  • [11] S. Dai et al., Nucl. Fusion 56, 066005 (2016).
  • [12] W. Möller et al., Comput. Phys. Commun. 51, 355 (1988).