Free-boundary equilibrium and stability of snowflake diverted and negative triangularity plasmas in the TCV tokamak

摘要

The TCV experimental campaign aims at studying H-mode plasmas and ELM behavior in various diverted configurations including equilibria with negative triangularity and snowflake divertor. Although the TCV tokamak is capable of generating plasma cross sections with a large variety of shapes, certain combinations are excluded by technical constraints. In particular, for diverted configurations, the strike points should be placed in regions covered by graphite tiles, which can support the local power densities, and avoid port windows.