H-mode scrape-off layer power width in the TCV tokamak

Abstract Obtaining acceptable conditions at the divertor targets of a next-step fusion experiment based on tokamak concept is expected to be particularly challenging because small predicted value plasma power exhaust channel width. An increased confidence in this prediction important forestall any issue and developing corresponding solutions. With present relying empirical scaling laws data from six tokamaks, letter tests these an additional device, TCV tokamak. Estimates width, ? q , Thomson scattering measurements electron temperature density profiles, correlate well with outer target infrared thermography. Reasonable agreement multi-device found only when including both crossing separatrix Greenwald fraction as regression parameters. TCV’s 2 3 times smaller than spherical tokamaks for same poloidal field. The inclusion would, therefore, require retention explicit aspect ratio dependence, consequences all other dependencies.