Abstract
Abstract
A set of dedicated H-mode discharges with constant heating power combining Neutral Beam Injection and Electron Cyclotron Resonance Heating have been executed at the ASDEX Upgrade tokamak using a high triangularity magnetic geometry in order to investigate the impact of filamentary transport to divertor and non-divertor components. The evolution of upstream scrape-off layer (SOL) profiles have been correlated with dedicated separatrix quantities, mostly with the turbulence control parameter
α
t
(Eich and Manz 2021 Nucl. Fusion
61 086016) describing the turbulence level at the separatrix. With increasing
α
t
, a broadening of the upstream density profiles in the near-SOL together with the formation of a density shoulder in the far-SOL have been observed. This phenomenon is associated with an enhanced filamentary transport dominating the radial turbulent transport in the far-SOL and confirmed by means of the cooling water calorimetry on non-divertor components. The probe measurements conducted with the ball-pen probe-head mounted on the midplane manipulator and a retarding-field analyzer close to the limiter surface indicate that the key mechanism increasing the radial filamentary transport to the first wall is an increase of the particle flux
Γ
r
,
fil
, caused primarily by the packing fraction
f
PF
,
fil
and the filament density
n
e
,
fil
. At the same time, the electron temperature
T
e
and ion temperature
T
i
measured close to the limiter surface show only small variations above
α
t
> 0.5. Both the filamentary heat flux and the gross erosion derived from the first wall probe measurements reach a magnitude that should be considered in the design of future fusion reactors.
Funder
HORIZON EUROPE Climate, Energy and Mobility