Predictions of alpha heating in ITER L-mode and H-mode DT plasmas are generated using the PTRANSP code. The baseline toroidal field (5.3 T), plasma current ramped to 15 MA and a flat electron density profile ramped to Greenwald fraction 0.85 are assumed. Various combinations of external heating by negative ion neutral beam injection, ion cyclotron resonance and electron cyclotron resonance are assumed to start half-way up the density ramp with the full power planned (Pext = 73 MW). 50 s later the power is reduced to 50 MW to increase QDT, and to prevent excessive heat flow to the divertor and walls as the alpha heating increases. The time evolution of plasma temperatures and bulk toroidal rotation vφ are predicted assuming GLF23 and boundar...
In order to prepare adequate current ramp-up and ramp-down scenarios for ITER, present experiments f...
In order to prepare adequate current ramp-up and ramp-down scenarios for ITER, present experiments f...
A number of proposed tokamak thermal transport models are tested by comparing their predictions with...
Performance in H-mode DT plasmas in ITER with various choices of heating systems are predicted and c...
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...
Predictive simulations of ITER [R. Aymar et al., Plasma Phys. Control. Fusion 44, 519 2002] discharg...
The pre-fusion power operation 1 phase of ITER is planned to be characterized by electron cyclotron ...
In this paper we provide evidence that, for fusion energy production, advanced scenarios based on th...
The TRANSP code is used to construct comprehensive, self-consistent models for ITER discharges. Plas...
The optimum conditions for access to and sustainment of H-mode plasmas and their expected plasma par...
The dynamics for the transition from L-mode to a stationary high QDT H-mode regime in ITER is expect...
The current ramp-up phase of ITER demonstration discharges, performed at JET, is analysed and the ca...
Currently, plasmas with internal transport barriers (ITBs) appear the most likely candidates for ste...
The understanding of anomalous transport mechanisms in magnetically confined plasmas is one of the m...
In order to prepare adequate current ramp-up and ramp-down scenarios for ITER, present experiments f...
In order to prepare adequate current ramp-up and ramp-down scenarios for ITER, present experiments f...
A number of proposed tokamak thermal transport models are tested by comparing their predictions with...
Performance in H-mode DT plasmas in ITER with various choices of heating systems are predicted and c...
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...
Predictive simulations of ITER [R. Aymar et al., Plasma Phys. Control. Fusion 44, 519 2002] discharg...
The pre-fusion power operation 1 phase of ITER is planned to be characterized by electron cyclotron ...
In this paper we provide evidence that, for fusion energy production, advanced scenarios based on th...
The TRANSP code is used to construct comprehensive, self-consistent models for ITER discharges. Plas...
The optimum conditions for access to and sustainment of H-mode plasmas and their expected plasma par...
The dynamics for the transition from L-mode to a stationary high QDT H-mode regime in ITER is expect...
The current ramp-up phase of ITER demonstration discharges, performed at JET, is analysed and the ca...
Currently, plasmas with internal transport barriers (ITBs) appear the most likely candidates for ste...
The understanding of anomalous transport mechanisms in magnetically confined plasmas is one of the m...
In order to prepare adequate current ramp-up and ramp-down scenarios for ITER, present experiments f...
In order to prepare adequate current ramp-up and ramp-down scenarios for ITER, present experiments f...
A number of proposed tokamak thermal transport models are tested by comparing their predictions with...