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

the TCV team, EUROfusion MST1 Team, Arthur Perek

Onderzoeksoutput: Bijdrage aan tijdschriftTijdschriftartikelAcademicpeer review

19 Citaten (Scopus)
102 Downloads (Pure)

Samenvatting

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

Duik in de onderzoeksthema's van 'Progress toward divertor detachment on TCV within H-mode operating parameters'. Samen vormen ze een unieke vingerafdruk.

Citeer dit