Progress toward divertor detachment on TCV within H-mode operating parameters

TCV team, EUROfusion MST1 team, Arthur Perek

Research output: Contribution to journalArticleAcademicpeer-review

1 Citation (Scopus)
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Abstract

Recent experiments on Tokamak à Configuration Variable have made significant progress toward partial detachment of the outer divertor in neutral beam heated H-mode plasmas in conventional and alternative divertor configurations. The heating power required to enter H-mode was measured in a range of divertor configurations. It is found that at the core densities most favourable for H-mode access, the L-H threshold power is largely independent of the poloidal flux expansion and major radius of the outer divertor, and in the snowflake minus configuration. A factor 2 reduction in the outer divertor power load was achieved in ELM-free (using a fuelling and nitrogen seeding) and ELMy (using nitrogen seeding) H-mode plasmas. No significant reduction in the outer divertor particle flux was achieved in the ELM-free scenarios, compared with ∼30% reduction in the most strongly detached ELMy cases. The poloidal flux expansion at the outer divertor was not found to significantly alter the cooling of the divertor in the ELM-free scenarios.

Original languageEnglish
Article number065024
Number of pages19
JournalPlasma Physics and Controlled Fusion
Volume61
Issue number6
DOIs
Publication statusPublished - 16 May 2019

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detachment
Fluxes
Nitrogen
Plasmas
Fueling
poloidal flux
inoculation
configurations
Cooling
Heating
nitrogen
expansion
refueling
neutral beams
flux (rate)
Experiments
cooling
heating
radii
thresholds

Keywords

  • divertor
  • divertor detachment
  • plasma physics
  • TCV
  • tokamak

Cite this

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title = "Progress toward divertor detachment on TCV within H-mode operating parameters",
abstract = "Recent experiments on Tokamak {\`a} Configuration Variable have made significant progress toward partial detachment of the outer divertor in neutral beam heated H-mode plasmas in conventional and alternative divertor configurations. The heating power required to enter H-mode was measured in a range of divertor configurations. It is found that at the core densities most favourable for H-mode access, the L-H threshold power is largely independent of the poloidal flux expansion and major radius of the outer divertor, and in the snowflake minus configuration. A factor 2 reduction in the outer divertor power load was achieved in ELM-free (using a fuelling and nitrogen seeding) and ELMy (using nitrogen seeding) H-mode plasmas. No significant reduction in the outer divertor particle flux was achieved in the ELM-free scenarios, compared with ∼30{\%} reduction in the most strongly detached ELMy cases. The poloidal flux expansion at the outer divertor was not found to significantly alter the cooling of the divertor in the ELM-free scenarios.",
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author = "{TCV team, EUROfusion MST1 team} and J.R. Harrison and C. Theiler and O. F{\'e}vrier and Oliviera, {H. De} and R. Maurizio and K. Verhaegh and Arthur Perek and A. Karpushov and B. Lipschultz and B.P. Duval and X. Feng and S. Henderson and B. Labit and B. Linehan and A. Merle and H. Reimerdes and U. Sheikh and C. Tsui and W.A.J. Vijvers and C. W{\"u}thrich",
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Progress toward divertor detachment on TCV within H-mode operating parameters. / TCV team, EUROfusion MST1 team ; Perek, Arthur.

In: Plasma Physics and Controlled Fusion, Vol. 61, No. 6, 065024, 16.05.2019.

Research output: Contribution to journalArticleAcademicpeer-review

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AU - TCV team, EUROfusion MST1 team

AU - Harrison, J.R.

AU - Theiler, C.

AU - Février, O.

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AU - Maurizio, R.

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AU - Karpushov, A.

AU - Lipschultz, B.

AU - Duval, B.P.

AU - Feng, X.

AU - Henderson, S.

AU - Labit, B.

AU - Linehan, B.

AU - Merle, A.

AU - Reimerdes, H.

AU - Sheikh, U.

AU - Tsui, C.

AU - Vijvers, W.A.J.

AU - Wüthrich, C.

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N2 - Recent experiments on Tokamak à Configuration Variable have made significant progress toward partial detachment of the outer divertor in neutral beam heated H-mode plasmas in conventional and alternative divertor configurations. The heating power required to enter H-mode was measured in a range of divertor configurations. It is found that at the core densities most favourable for H-mode access, the L-H threshold power is largely independent of the poloidal flux expansion and major radius of the outer divertor, and in the snowflake minus configuration. A factor 2 reduction in the outer divertor power load was achieved in ELM-free (using a fuelling and nitrogen seeding) and ELMy (using nitrogen seeding) H-mode plasmas. No significant reduction in the outer divertor particle flux was achieved in the ELM-free scenarios, compared with ∼30% reduction in the most strongly detached ELMy cases. The poloidal flux expansion at the outer divertor was not found to significantly alter the cooling of the divertor in the ELM-free scenarios.

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