Search

Radiative cooling is one of the main heat dissipation channels for magnetically confined fusion plasmas. In stellarators power exhaust control is complicated by the three-dimensional radiation distribution. Using a Gaussian Process Tomography routine, the two-dimensional radiation distribution in Wendelstein 7-X is reconstructed from the line-integrated bolometer data of one poloidal cross-section. These experimental tomograms are mapped to the field of view of the newly installed divertor bolometer cameras and compared to the toroidally separated local measurements to assess the toroidal radiation distribution. We observe peaking of the plasma radiated power density in the divertor region and steep toroidal gradients, especially at low radiated power fraction (up to ×8 increase in the emissivity along a ∼2m long flux tube). These results suggest the presence of significant toroidal radiation asymmetries within a stellarator half-module.

The low magnetic shear in the Wendelstein 7-X (W7-X) stellarator makes it feasible to shape the separatrix by the large islands constituting an island-divertor, and this can be exploited to access various magnetic configurations, including samples of different internal island sizes and locations. To investigate the configuration effects on the plasma confinement, a configuration scan was performed by changing the coil currents to vary the rotational transform between values $5/4$ and $5/6$ at the plasma boundary with different power levels (2, 4, 6 MW) of electron cyclotron resonance heating (ECRH) at a maximum plasma density of $8 \times 10^{19}\,\textrm{m}^{-2}$ . neutral beam injection (NBI) heating was also applied during some configurations of the scan to create a density ramp and access high densities beyond the X2 ECRH cutoff. For the magnetic configurations, where the $5/5$ and $5/6$ island chains were moved closer to separatrix but remaining inside the last closed flux surface, the electron cyclotron emission shows that an electron temperature, $T_{\mathrm e}$ , pedestal develops already during ECRH heated plasma buildup phase indicating a transport barrier, and the barrier sustains irrespective of changed plasma heating conditions such as NBI in the later part of discharge. The transport barrier is broken by subsequent fast crashes, observed with multiple plasma diagnostics with characteristics such as tokamak edge localized modes, and the corresponding crash amplitude and frequency vary with plasma pressure. The impact of the transport barrier on plasma confinement can be seen through the increased core $T_{\mathrm e}$ profile, which could be responsible for the overall increase in the stored diamagnetic energy by approximately 10% for these configurations. After the plasma heating is terminated, a backwards transition to a degraded confinement state is also observed. These observations indicate a configuration triggered high confinement mode in low shear W7-X. This work focuses on the occurrence of this transport barrier for different magnetic configurations and its relation to internal magnetic islands.