Fig. 3: Divertor heat flux width with different out-mid-plane poloidal magnetic field Bp and turbulence at the separatrix.
From: How turbulence spreading improves power handling in quiescent high confinement fusion plasmas
a Comparison of measured divertor heat flux width with experimental multi-machine scaling regression #1452 (black); b Ratio of measured divertor heat flux and Eich scaling as a function of BES measured low-frequency IDD turbulence amplitude \(\delta n/n\) close to the separatrix. Note that both ion diamagnetic direction (IDD) and electron diamagnetic direction (EDD) modes coexist inside the separatrix, and only IDD mode exists in the open field line region. The solid bullets are the heat flux width measured from Infrared Imaging Systems (IR camera), and the empty bullets are measured from Divertor Langmuir Probes. The errorbars are estimated by performing bootstrapping simulations for the heat flux widths measured by Divertor Langmuir Probes.
