Electron cyclotron current drive (ECCD) calculations for the case of the ITER electron cyclotron resonant heating upper port launcher are presented making use of a quasi-optical (QO) code (Balakin et al 2008 Nucl. Fusion 48 065003). The QO code describes accurately the behaviour of the wave beam in the electron cyclotron resonance layer, taking into account spatial inhomogeneity and dispersion. The ECCD efficiency is obtained using the adjoint calculation as presented by (Lin-Liu et al 2003 Phys. Plasmas 10 4064). The results show a broadening of the EC driven current density profiles in the range 15-30% as compared with beam-tracing calculations using TORBEAM. Consistently, peak driven current density values are found to be decreased by 10...
In the Wendelstein 7-X stellarator, up to 7MW of power are delivered to the plasma by an electron cy...
The ITER baseline design relies on ECCD to stabilize confinementdegrading disruptive NTMs [1]. Howev...
Neoclassical tearing modes (NTMs) deteriorate high-pressure tokamak plasma confinement and can be su...
Electron cyclotron current drive (ECCD) calculations for the case of the ITER electron cyclotron res...
Electron cyclotron (EC) power has technological and physics advantages for heating and current drive...
The existing ECWGB code which describes the quasi-optical propagation of a Gaussian beam of electron...
A quasi-optical description of the propagation and damping of the slowly varying wave amplitude acro...
One of the main aims of the ITER electron cyclotron resonance heating (ECRH) system, in particular o...
One of the main aims of the ITER electron cyclotron resonance heating (ECRH) system, in particular o...
Optimal design and use of electron cyclotron heating requires that accurate and relatively quick com...
The performance of the ITER standard scenario can be reduced due to neoclassical tear-ing modes [1]....
Electron cyclotron resonance heating (ECRH) and electron cyclotron current drive (ECCD) are used to ...
Efficient off-axis current drive is crucial for economic, steady-state tokamak fusion power plants. ...
The current drive efficiency of electron cyclotron (EC) wave is typically low compared with other RF...
Neoclassical tearing modes (NTMs) deteriorate high-pressure tokamak plasma confinement and can be su...
In the Wendelstein 7-X stellarator, up to 7MW of power are delivered to the plasma by an electron cy...
The ITER baseline design relies on ECCD to stabilize confinementdegrading disruptive NTMs [1]. Howev...
Neoclassical tearing modes (NTMs) deteriorate high-pressure tokamak plasma confinement and can be su...
Electron cyclotron current drive (ECCD) calculations for the case of the ITER electron cyclotron res...
Electron cyclotron (EC) power has technological and physics advantages for heating and current drive...
The existing ECWGB code which describes the quasi-optical propagation of a Gaussian beam of electron...
A quasi-optical description of the propagation and damping of the slowly varying wave amplitude acro...
One of the main aims of the ITER electron cyclotron resonance heating (ECRH) system, in particular o...
One of the main aims of the ITER electron cyclotron resonance heating (ECRH) system, in particular o...
Optimal design and use of electron cyclotron heating requires that accurate and relatively quick com...
The performance of the ITER standard scenario can be reduced due to neoclassical tear-ing modes [1]....
Electron cyclotron resonance heating (ECRH) and electron cyclotron current drive (ECCD) are used to ...
Efficient off-axis current drive is crucial for economic, steady-state tokamak fusion power plants. ...
The current drive efficiency of electron cyclotron (EC) wave is typically low compared with other RF...
Neoclassical tearing modes (NTMs) deteriorate high-pressure tokamak plasma confinement and can be su...
In the Wendelstein 7-X stellarator, up to 7MW of power are delivered to the plasma by an electron cy...
The ITER baseline design relies on ECCD to stabilize confinementdegrading disruptive NTMs [1]. Howev...
Neoclassical tearing modes (NTMs) deteriorate high-pressure tokamak plasma confinement and can be su...