Glenn Bateman

Learn More
Performance of the ITER is anticipated to be highly sensitive to the edge plasma condition. The edge pedestal in ITER needs to be predicted from an integrated simulation of the necessary first-principles, multi-scale physics codes. The mission of the SciDAC Fusion Simulation Project (FSP) Prototype Center for Plasma Edge Simulation (CPES) is to deliver such(More)
The predictions of gyrokinetic and gyroouid simulations of ion-temperature-gradient (ITG) instability and turbulence in tokamak plasmas as well as some tokamak plasma thermal transport models, which have been widely used for predicting the performance of the proposed ITER tokamak, are compared. These comparisons provide information on eeects of diierences(More)
A new predictive computer simulation tool targeting the development of the H-mode pedestal at the plasma edge in tokamaks and the triggering and dynamics of edge localized modes (ELMs) is presented in this report. This tool brings together, in a coordinated and effective manner, several first-principles physics simulation codes, stability analysis packages,(More)
The NUBEAM module is a comprehensive computational model for Neutral Beam Injection (NBI) in tokamaks. It is used to compute power deposition, driven current, momentum transfer, fueling, and other profiles in tokamak plasmas due to NBI. NUBEAM computes the time-dependent deposition and slowing down of the fast ions produced by NBI, taking into consideration(More)
Predictions of the recently developed paleoclassical transport model are compared with data from many toroidal plasma experiments: electron heat diffusivity in DIII-D, C-Mod and NSTX ohmic and near-ohmic plasmas; transport modeling of DIII-D ohmic-level discharges and of the RTP ECH " stair-step " experiments with eITBs at low order rational surfaces;(More)
In solving the 1D (flux surface averaged) transport equations for the temperatures, magnetic fields, and densities in the ''evolving equilibrium " description of a tokamak [1], one increasingly encounters highly nonlinear thermal conductivity and diffusivity functions, such as GLF23 [2], that have a strong and non-analytic dependence on the temperature(More)
A model is proposed for the edge electron temperature profile Te(ρ) in high (H) confinement mode, diverted tokamak plasmas based on the paleoclassical model for the minimum radial electron heat transport. Moving inward from the separatrix, Te profile predictions are: first an increasing Te gradient with ηe ≡ d ln Te/d ln ne 2, a maximum |∇Te| where q drops(More)
COMPACT IGNITION TOKAMAK PHYSICS AND ENGINEERING BASIS. The Compact Ignition Tokamak (CIT) is a high-Beld, compact tokamak design whose objective is the study of physics issues associated with burning plasmas. The toroidal and poloidal field coils employ a copper-steel laminate, mamrfacmred by explosive-bonding techniques, to support the forces generated by(More)