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

TCV team, EUROfusion MST1 team, Arthur Perek

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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.

Originele taal-2Engels
Artikelnummer065024
Aantal pagina's19
TijdschriftPlasma Physics and Controlled Fusion
Volume61
Nummer van het tijdschrift6
DOI's
StatusGepubliceerd - 16 mei 2019

Vingerafdruk

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

Citeer dit

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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, Nr. 6, 065024, 16.05.2019.

Onderzoeksoutput: Bijdrage aan tijdschriftTijdschriftartikelAcademicpeer review

TY - JOUR

T1 - Progress toward divertor detachment on TCV within H-mode operating parameters

AU - TCV team, EUROfusion MST1 team

AU - Harrison, J.R.

AU - Theiler, C.

AU - Février, O.

AU - Oliviera, H. De

AU - Maurizio, R.

AU - Verhaegh, K.

AU - Perek, Arthur

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.

PY - 2019/5/16

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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.

AB - 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.

KW - divertor

KW - divertor detachment

KW - plasma physics

KW - TCV

KW - tokamak

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