The quasi-optical ECWGB code is used to predict the design require-ments and performances of the ITER-ECRF Upper Launcher, that has as its main goal the stabilization of (3,2) and (2,1) neoclassical tearing modes. Detailed calculations are presented here for various ITER-FEAT relevant plasma scenarios. The required steering range and the behavior of figures of merit for NTMs stabilization are shown for both the upper and lower row of mirrors, pointing out that larger efficiencies are obtained by launching from the lower row. The effect of the local beam size on the width of the driven current profile is underlined. 1
The design of a remote steering (RS) variant of the electron cyclotron heating (ECH) upper port laun...
The ITER ECRH system consists of 24 gyrotrons with up to 24 MW installed millimeter wave heating pow...
The ITER ECRH system consists of 24 gyrotrons with up to 24 MW installed millimeter wave heating pow...
Abstract. The purpose of the ITER electron cyclotron resonance heating (ECRH) upper port launcher is...
The purpose of the ITER electron cyclotron resonance heating (ECRH) upper port launcher will be to s...
The design of the ITER electron cyclotron launchers recently reached the preliminary design level - ...
The 24 MW ITER Electron Cyclotron (EC) Heating and Current Drive (H&CD) system, operating at 170 GHz...
Abstract. The ITER ECH heating and current drive system delivers 24MW (170GHz), which can be directe...
Electron cyclotron waves injected from an antenna located in the upper part of the vessel will be em...
The main objective of the ITER ECRH upper launcher (UL) is to control magnetohydrodynamic activity, ...
The ITER ECH upper launcher is devoted to directing up to 8 2NM beams per port plug over half of the...
The relativistic and self-consistent ray tracing and Fokker-Planck code BANDIT-3D is used to study t...
Four of the 16 ITER upper port plugs will be devoted to electron cyclotron resonance heating (ECRH) ...
Electron cyclotron current drive will become the main scheme on ITER for the stabilization of neocla...
The design of the ITER ECRH system provides 20 MW millimeter wave power for central plasma ...
The design of a remote steering (RS) variant of the electron cyclotron heating (ECH) upper port laun...
The ITER ECRH system consists of 24 gyrotrons with up to 24 MW installed millimeter wave heating pow...
The ITER ECRH system consists of 24 gyrotrons with up to 24 MW installed millimeter wave heating pow...
Abstract. The purpose of the ITER electron cyclotron resonance heating (ECRH) upper port launcher is...
The purpose of the ITER electron cyclotron resonance heating (ECRH) upper port launcher will be to s...
The design of the ITER electron cyclotron launchers recently reached the preliminary design level - ...
The 24 MW ITER Electron Cyclotron (EC) Heating and Current Drive (H&CD) system, operating at 170 GHz...
Abstract. The ITER ECH heating and current drive system delivers 24MW (170GHz), which can be directe...
Electron cyclotron waves injected from an antenna located in the upper part of the vessel will be em...
The main objective of the ITER ECRH upper launcher (UL) is to control magnetohydrodynamic activity, ...
The ITER ECH upper launcher is devoted to directing up to 8 2NM beams per port plug over half of the...
The relativistic and self-consistent ray tracing and Fokker-Planck code BANDIT-3D is used to study t...
Four of the 16 ITER upper port plugs will be devoted to electron cyclotron resonance heating (ECRH) ...
Electron cyclotron current drive will become the main scheme on ITER for the stabilization of neocla...
The design of the ITER ECRH system provides 20 MW millimeter wave power for central plasma ...
The design of a remote steering (RS) variant of the electron cyclotron heating (ECH) upper port laun...
The ITER ECRH system consists of 24 gyrotrons with up to 24 MW installed millimeter wave heating pow...
The ITER ECRH system consists of 24 gyrotrons with up to 24 MW installed millimeter wave heating pow...