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

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, A.

AU - Karpushov, A.

AU - Lipschultz, B.

AU - Duval, B. P.

AU - Henderson, S.

AU - Labit, B.

AU - Linehan, B.

AU - Merle, A.

AU - Reimerdes, H.

AU - Sheikh, U.

AU - Tsui, C. K.

AU - Vijvers, W. A.J.

AU - Wüthrich, C.

N1 - © 2019 Crown copyright. Reproduced with the permission of the Controller of Her Majesty's Stationery Office

PY - 2019/5/16

Y1 - 2019/5/16

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

UR - http://www.scopus.com/inward/record.url?scp=85069447586&partnerID=8YFLogxK

U2 - 10.1088/1361-6587/ab140e

DO - 10.1088/1361-6587/ab140e

M3 - Article

AN - SCOPUS:85069447586

SN - 0741-3335

VL - 61

JO - Plasma Physics and Controlled Fusion

JF - Plasma Physics and Controlled Fusion

IS - 6

M1 - 065024

ER -