Transport Physics of Hybrid Scenario Plasmas in the International Multi-Tokamak Database and Implications for ITER
Transport in Hybrid plasmas in the international ITPA profile database is studied. The TRANSP code is used to deduce energy, angular momentum, and density transport. The physics-based predictive models GLF23 and MMM95 are used to simulate temperature and toroidal velocity profiles assuming turbulence driven by ITG/TEM. The GYRO gyrokinetic code is used for nonlinear turbulence simulations of the energy, angular momentum, and species transport during quasi-steady state phases. Modeling and simulation results are compared to experimental measurements with limited agreement, indicating that further work is still required. Effects of varying the negative ion neutral beam injection into simulated ITER Hybrid plasmas indicates that below-axis aiming can maintain the q profile above unity.