Performance in H-mode DT plasmas in ITER with various choices of heating systems are predicted and compared. Combinations of external heating by Negative Ion Neutral Beam Injection (NNBI), Ion Cyclotron Range of Frequencies (ICRF), and Electron Cyclotron Heating (ECH) are assumed. Scans with a range of physics assumptions about boundary temperatures in the edge pedestal, alpha ash transport, and toroidal momentum transport are used to indicate effects of uncertainties. Time-dependent integrated modeling with the PTRANSP code is used to predict profiles of heating, beam torque, and plasma profiles. The GLF23 model is used to predict temperature profiles. Either GLF23 or the assumption of a constant ratio for χø/χi is used to predict toroidal...
A number of proposed tokamak thermal transport models are tested by comparing their predictions with...
Hybrid scenario performance in ITER is studied with the CRONOS integrated modelling suite, using the...
ABSTRACT. Heating and current drive (H&CD) systems must fulfill several roles in ITER operating ...
Performance in H-mode DT plasmas in ITER with various choices of heating systems are predicted and c...
Time-dependent integrated predictive modelling is carried out using the PTRANSP code to predict fusi...
Predictions of alpha heating in ITER L-mode and H-mode DT plasmas are generated using the PTRANSP co...
Predictive simulations of ITER [R. Aymar et al., Plasma Phys. Control. Fusion 44, 519 2002] discharg...
A number of proposed tokamak thermal transport models are tested by comparing their predictions with...
Simulations of JET and AUG HS with the GLF23 model show that the observed core confinement improveme...
The current ramp-up phase of ITER demonstration discharges, performed at JET, is analysed and the ca...
The optimum conditions for access to and sustainment of H-mode plasmas and their expected plasma par...
The values of Q = (fusion power)/(auxiliary heating power) predicted for ITER by three different met...
Abstract The experiment described in this paper is aimed at characterization of ELMy H-mode discharg...
Abstract Benchmarking of full-wave solvers for ICRF simulations is performed using plasma profiles a...
The TRANSP code is used to construct comprehensive, self-consistent models for ITER discharges. Plas...
A number of proposed tokamak thermal transport models are tested by comparing their predictions with...
Hybrid scenario performance in ITER is studied with the CRONOS integrated modelling suite, using the...
ABSTRACT. Heating and current drive (H&CD) systems must fulfill several roles in ITER operating ...
Performance in H-mode DT plasmas in ITER with various choices of heating systems are predicted and c...
Time-dependent integrated predictive modelling is carried out using the PTRANSP code to predict fusi...
Predictions of alpha heating in ITER L-mode and H-mode DT plasmas are generated using the PTRANSP co...
Predictive simulations of ITER [R. Aymar et al., Plasma Phys. Control. Fusion 44, 519 2002] discharg...
A number of proposed tokamak thermal transport models are tested by comparing their predictions with...
Simulations of JET and AUG HS with the GLF23 model show that the observed core confinement improveme...
The current ramp-up phase of ITER demonstration discharges, performed at JET, is analysed and the ca...
The optimum conditions for access to and sustainment of H-mode plasmas and their expected plasma par...
The values of Q = (fusion power)/(auxiliary heating power) predicted for ITER by three different met...
Abstract The experiment described in this paper is aimed at characterization of ELMy H-mode discharg...
Abstract Benchmarking of full-wave solvers for ICRF simulations is performed using plasma profiles a...
The TRANSP code is used to construct comprehensive, self-consistent models for ITER discharges. Plas...
A number of proposed tokamak thermal transport models are tested by comparing their predictions with...
Hybrid scenario performance in ITER is studied with the CRONOS integrated modelling suite, using the...
ABSTRACT. Heating and current drive (H&CD) systems must fulfill several roles in ITER operating ...