Modeling Tokamak Discharges during Startup in DIII-D and Predictions for ITER*

The PTRANSP code is being developed for improving predictions of ITER and future Tokamaks [1]. Important goals are predicting plasma performance as well as safe and efficient startup and termination. PTRANSP is being tested on experiments in DIII-D to explore and optimize plasma startup and termination, and to benchmark of transport. An important aspect is to model the boundary accurately since parameters such as the flux consumption and induction {\it li} can vary sensitively on the boundary shape. PTRANSP is being modified to allow for direct input of the flux in R, Z space (from EFIT) instead of using Fourier moments of the boundary. PTRANSP will write quantities such as the inductance and surface voltage at the separatrix surface as well as the flux boundary usually used in TRANSP. The predictive capabilities are being improved also. These include models for predicting temperatures, densities, and toroidal momentum. Predictions for ITER will be discussed. \\ {[}1{]} R.V. Budny, Nuclear Fusion {\bf 49} (2009) 085008.