This proposal is based on a methodological framework developed at the ASDEX Upgrade tokamak. For these experiments, a very typical high confinement mode discharge is targeted, well within the experimental comfort zone of the machine. It is important to avoid strong magneto-hydrodynamic modes during these experiments. The first task is to find optimal settings for the NBI modulation and to perform a scan in toroidal rotation by balancing co- and counter-current neutral beam injection, ranging from small rotation plasmas to higher rotation plasmas, while keeping the total heating, background gradients, and dimensionless parameters as constant as possible. Second, based on the previous scenarios, a scan in Te/Ti will be performed by adding electron cyclotron heating. These scans will provide high-quality momentum transport data, with variations in the most ITER-relevant transport and turbulence regimes, ranging from low rotation plasmas to higher ones, and including a transition from ion-heated to electron-heated plasmas. Third, comparison discharges with high shaping and fueling will be performed to scan the pedestal gradients and potentially obtain data points within a type-II ELM regime, which is a promising candidate for future reactor operation. Finally, the effect of the effective ion charge on momentum transport will be measured to compare the results to other machines, such as the AUG tokamak, which differs from DIII-D in wall material (metal instead of carbon). This will be done by adding additional carbon via an impurity dropper. During the experiments, dedicated discharges and piggyback measurements will be conducted for turbulence measurements. This will allow for the extraction of residual stress measurements from the fluctuating velocity fields, enabling direct validation of the two different experimental techniques.