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Modeling of COMPASS tokamak divertor liquid metal experiments

J. Horacek, R. Dejarnac, J. Cecrdle, D. Tskhakaya, A. Vertkov, J. Cavalier, P. Vondracek, M. Jerab, P. Barton, Guido Van Oost (UGent) , et al.
(2020) NUCLEAR MATERIALS AND ENERGY. 25.
Author
Organization
Abstract
Two small liquid metal targets based on the capillary porous structure were exposed to the divertor plasma of the tokamak COMPASS. The first target was wetted by pure lithium and the second one by a lithium-tin alloy, both releasing mainly lithium atoms (sputtering and evaporation) when exposed to plasma. Due to poorly conductive target material and steep surface inclination (implying the surface-perpendicular plasma heat flux 12-17 MW/m(2)) for 0.1-0.2 s, the LiSn target has reached 900 degrees C under ELMy H-mode. A model of heat conduction is developed and serves to evaluate the lithium sputtering and evaporation and, thus, the surface cooling by the released lithium and consequent radiative shielding. In these conditions, cooling of the surface by the latent heat of vapor did not exceed 1 MW/m(2). About 10(19) lithium atoms were evaporated (comparable to the COMPASS 1 m(3) plasma deuterium content), local Li pressure exceeded the deuterium plasma pressure. Since the radiating Li vapor cloud spreads over a sphere much larger than the hot spot, its cooling effect is negligible (0.2 MW/m(2)). We also predict zero lithium prompt redeposition, consistent with our observation.Y
Keywords
THERMODYNAMIC PROPERTIES, POINT, THERMOGRAPHY, LITHIUM, HEAT, ITER, Tokamak, Divertor, Liquid metals, Plasma facing components

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MLA
Horacek, J., et al. “Modeling of COMPASS Tokamak Divertor Liquid Metal Experiments.” NUCLEAR MATERIALS AND ENERGY, vol. 25, 2020, doi:10.1016/j.nme.2020.100860.
APA
Horacek, J., Dejarnac, R., Cecrdle, J., Tskhakaya, D., Vertkov, A., Cavalier, J., … Panek, R. (2020). Modeling of COMPASS tokamak divertor liquid metal experiments. NUCLEAR MATERIALS AND ENERGY, 25. https://doi.org/10.1016/j.nme.2020.100860
Chicago author-date
Horacek, J., R. Dejarnac, J. Cecrdle, D. Tskhakaya, A. Vertkov, J. Cavalier, P. Vondracek, et al. 2020. “Modeling of COMPASS Tokamak Divertor Liquid Metal Experiments.” NUCLEAR MATERIALS AND ENERGY 25. https://doi.org/10.1016/j.nme.2020.100860.
Chicago author-date (all authors)
Horacek, J., R. Dejarnac, J. Cecrdle, D. Tskhakaya, A. Vertkov, J. Cavalier, P. Vondracek, M. Jerab, P. Barton, Guido Van Oost, M. Hron, V Weinzettl, D. Sestak, S. Lukes, J. Adamek, A. Prishvitsin, M. Iafratti, Y. Gasparyan, Y. Vasina, D. Naydenkova, J. Seidl, E. Gauthier, G. Mazzitelli, M. Komm, J. Gerardin, J. Varju, M. Tomes, S. Entler, J. Hromadka, and R. Panek. 2020. “Modeling of COMPASS Tokamak Divertor Liquid Metal Experiments.” NUCLEAR MATERIALS AND ENERGY 25. doi:10.1016/j.nme.2020.100860.
Vancouver
1.
Horacek J, Dejarnac R, Cecrdle J, Tskhakaya D, Vertkov A, Cavalier J, et al. Modeling of COMPASS tokamak divertor liquid metal experiments. NUCLEAR MATERIALS AND ENERGY. 2020;25.
IEEE
[1]
J. Horacek et al., “Modeling of COMPASS tokamak divertor liquid metal experiments,” NUCLEAR MATERIALS AND ENERGY, vol. 25, 2020.
@article{8711951,
  abstract     = {{Two small liquid metal targets based on the capillary porous structure were exposed to the divertor plasma of the tokamak COMPASS. The first target was wetted by pure lithium and the second one by a lithium-tin alloy, both releasing mainly lithium atoms (sputtering and evaporation) when exposed to plasma. Due to poorly conductive target material and steep surface inclination (implying the surface-perpendicular plasma heat flux 12-17 MW/m(2)) for 0.1-0.2 s, the LiSn target has reached 900 degrees C under ELMy H-mode. A model of heat conduction is developed and serves to evaluate the lithium sputtering and evaporation and, thus, the surface cooling by the released lithium and consequent radiative shielding. In these conditions, cooling of the surface by the latent heat of vapor did not exceed 1 MW/m(2). About 10(19) lithium atoms were evaporated (comparable to the COMPASS 1 m(3) plasma deuterium content), local Li pressure exceeded the deuterium plasma pressure. Since the radiating Li vapor cloud spreads over a sphere much larger than the hot spot, its cooling effect is negligible (0.2 MW/m(2)). We also predict zero lithium prompt redeposition, consistent with our observation.Y}},
  articleno    = {{100860}},
  author       = {{Horacek, J. and Dejarnac, R. and Cecrdle, J. and Tskhakaya, D. and Vertkov, A. and Cavalier, J. and Vondracek, P. and Jerab, M. and Barton, P. and Van Oost, Guido and Hron, M. and Weinzettl, V and Sestak, D. and Lukes, S. and Adamek, J. and Prishvitsin, A. and Iafratti, M. and Gasparyan, Y. and Vasina, Y. and Naydenkova, D. and Seidl, J. and Gauthier, E. and Mazzitelli, G. and Komm, M. and Gerardin, J. and Varju, J. and Tomes, M. and Entler, S. and Hromadka, J. and Panek, R.}},
  issn         = {{2352-1791}},
  journal      = {{NUCLEAR MATERIALS AND ENERGY}},
  keywords     = {{THERMODYNAMIC PROPERTIES,POINT,THERMOGRAPHY,LITHIUM,HEAT,ITER,Tokamak,Divertor,Liquid metals,Plasma facing components}},
  language     = {{eng}},
  pages        = {{8}},
  title        = {{Modeling of COMPASS tokamak divertor liquid metal experiments}},
  url          = {{http://doi.org/10.1016/j.nme.2020.100860}},
  volume       = {{25}},
  year         = {{2020}},
}
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