Investigating of the heating transport models in DIIID ITER ramp up experiments

The confidence in ramp up scenario design of the China Fusion Engineering Test Reactor (CFETR) can be significantly enhanced using validated transport models to predict the current profile and temperature profile. In the Tokamak Simulation Code (TSC), two semi-empirical energy transport models (the Coppi-Tang and BGB model) and three theory-based models (the GLF23, MMM95 and CDBM model) are validated on several CFETR relevant ramp up discharges, including three DIII-D ITER-like ramp up discharges. The plasma shape is controlled to be in good agreement with experiments using the RZIP control system. For the ohmic heating phase of DIII-D discharges (L-mode), the MMM95 and BGB model overestimate the ℓ_i within a maximum discrepancy of 12.56%, while the GLF23, Coppi-Tang and CDBM models underestimate the ℓ_i within a maximum discrepancy of -3.94%. For NBI heating phase of DIII-D discharges (H-mode), the experimental pedestal, NBI heating information and the Sauter current model are used in simulation. Including the influence of toroidal rotation during the NBI heating phase, the CDBM and GLF23 model can give good predictions for both the electron and ion temperature profiles, while the BGB and MMM95 model without rotation factor can only give good predictions for the electron temperature and underestimate β_p. Simulations with CDBM model yield the smallest discrepancy for ℓ_i and β_p. Comparing all models using standardized metrics, the Coppi-Tang model and CDBM model seem to be the favorable choices for the CFETR ramp up design in L- and H-mode, respectively. (author)