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

TitleProgress toward divertor detachment on TCV within H-mode operating parameters
Publication TypeJournal Article
Year of Publication2019
AuthorsJ.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
JournalPlasma 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 TitlePlasma Phys. Control. Fusion

Go back one page.