|Title||Progress toward divertor detachment on TCV within H-mode operating parameters|
|Publication Type||Journal Article|
|Year of Publication||2019|
|Authors||J.R Harrison, C. Theiler, O. Février, H. de Oliveira, R. Maurizio, K. Verhaegh, A. Perek, A. Karpushov, B. Lipschultz, W.AJ Vijvers, B.P Duval, X. Feng, S. Henderson, B. Labit, B. Linehan, A. Merle, H. Reimerdes, U. Sheikh, C.K Tsui, C. Wuthrich, TCV team, EUROfusion MST1 Team|
|Journal||Plasma Physics and Controlled Fusion|
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 similar to 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.
|Alternate Title||Plasma Phys. Control. Fusion|
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