Rich has sent an updated EFIT equilibrium for the DIII-D discharge 132014.03000. It has resolution of 129×129, kinetic equilibrium option enable and low EFIT error parameter. The TEQ code shows significantly lower residual in the near separatrix region as well.
Note that the plasma pressure profiles looks significantly different comparing to the lower resolution case at 3.023 sec (left figure below shows the derivate of the plasma pressure at 3.000 sec and right figure shows the derivative of the plasma pressure at 3.023 sec):
EFIT grid has been set to 129×129, number of iterations has been increased to 50, the namelist value for error has been decreased from 1.e-3 to 1.e-4. The resulting layout looks very similar. However, the normalized beta is reduced by about 3%. Analysis with TEQ still indicates relatively high residual error near the separatrix. This error might be related to different input options that might be associated with different account for the bootstrap current. There are differences in FF’ and q profiles that might be more difficult to understand. Some of equilibrium profiles are shown below. Left column shows profiles obtained with the new EFIT (129×129) run, while the left column shows profiles obtained with the old EFIT (65×65) run.
The tbl_diffusion_mode option is set to 3 to enable transition from FMCFM in the plasma core and old model in the SOL region. In addition, spacial variation is allowed in the SOL region by setting tbl_d_profile_on to 1. As result, the problem of accumulation of particles in the SOL region is resolved:
Problems identified in the case XGC-A02 remains at longer times (30 ion transit times in the case XGC-A02 vs 6 ion transit times in the case XGC-A01). The diffusivity remain rather high in the plasma core. Particles accumulate in the SOL region. It looks that the later problem has been introduced during recent code update and relates to the interpolation of tbl_* diffusivities used in the outer region of plasma and FMCFM diffivities in the plasma core.
Relatively large diffusivity in the plasma core is observed in this case. There is a density increase in the separatrix-SOL region that need to be understood. It is possible that longer simulation is necessary to relax the plasma profiles in the core.
Rich Groebner has provided information about total heating powers in the DIII-D discharges that are considered from modeling with the XGC-0 code. According to Rich:
Neutral beam injection was the only auxiliary heating on these discharges... I have supplied powers averaged over the entire time of interest.
132014 8.12 MW
132016 7.35 MW
132017 8.49 MW
132018 7.09 MW
Rich has also provided the plasma density and temperature profiles.