The 10 MW ECRH and CD System for W7-X

Abstract

Electron Cyclotron Resonance Heating (ECRH) is the main heating method for the Wendelstein 7-X Stellarator (W7-X), which is the next step device in the stellarator line of IPP and is presently under construction in the Greifswald branch of IPP. The experiment aims at demonstrating the inherent steady state capability of stellarators at reactor relevant plasma parameters. W7-X (major radius 5.5 m, minor radius 0.55 m) is equipped with a superconducting coil system operating at 3 T for steady state operation and a divertor for 10 MW steady state heat removal. A 10 MW ECRH plant with CWcapability at 140 GHz is under construction to meet the scientific objectives. The microwave power is generated by 10 gyrotrons with 1 MW each. A European R&D program aiming at the development of a prototype gyrotron for W7-X has been successfully terminated by fall of 2002. A prototype gyrotron with the same specifications was developed for W7-X at CPI (USA). Test results and limitations are reported. The distinct microwave beams from each gyrotron are combined and transmitted to the W7-X Stellarator ports by an open quasi-optical transmission system with high transmission efficiency, which runs at normal pressure and consists of water cooled imaging mirrors. Cold tests of a full size, uncooled prototype line and the related RF-diagnostics are presented. The microwave power is launched to the plasma through 10 synthetic diamond barrier windows and in-vessel quasi-optical plug-in launchers, which allow an independent steering of each beam. The commissioning of the ECRH plant is well under way and the status is presented.

Frontiers in the Application of RF Vacuum Electronics

“…The microwave sources (or gyrotrons) and their paired HVPSs need be several tens, or even hundreds, of meters distance from the fusion device, as its magnetic field required to achieve plasma confinement impacts the gyrotron operation if these are placed in close proximity. The microwave power is transmitted to the fusion device via evacuated waveguide [ 85 ] or quasi-optical [ 86 ] transmission systems. The 4.5-MW EC HCD system [ 87 ], [ 88 ] on the Tokamak â Configuration Variable (TCV) is an example of an operating plant, as shown in Fig.…”

Wendelstein 7-X Torus Hall Layout and System Integration

“…Plasma heating of W7-X is provided via ECRH [4], NBI and ICRH. The 10 ECRH gyrotrons are located outside the torus hall.…”