A long pulse electron cyclotron resonance heating (ECRH) system has been developed to meet the requirements of steady-state operation for the EAST superconducting tokamak, and the first EC wave was successfully injected into plasma during the 2015 spring campaign. The system is mainly composed of four 140 GHz gyrotron systems, 4 ITER-Like transmission lines, 4 independent channel launchers and corresponding power supplies, a water cooling, control & inter-lock system etc. Each gyrotron is expected to deliver a maximum power of 1 MW and be operated at 100-1000 s pulse lengths. The No.1 and No.2 gyrotron systems have been installed. In the initial commissioning, a series of parameters of 1 MW 1 s, 900 kW 10 s, 800 kW 95 s and 650 kW 753 s have been demonstrated successfully on the No.1 gyrotron system based on calorimetric dummy load measurements. Significant plasma heating and MHD instability suppression effects were observed in EAST experiments. In addition, high confinement (H-mode) discharges triggered by ECRH were obtained.

https://iopscience.iop.org/article/10.1088/1009-0630/18/4/19/pdf

Development and Preliminary Commissioning Results of a Long Pulse 140 GHz ECRH System on EAST Tokamak (Invited)

The development of electron cyclotron resonance heating (ECRH)-electron cyclotron current drive (ECCD) as a tool for suppression of plasma instabilities requires that the millimeter-wave beams used...

A New Launcher for Real-Time ECRH Experiments on FTU

To combine powers from a set of gyrotrons and to switch the combined wave beam between a number of output channels, various kinds of multiplexers can be used. Especially, narrow-band frequency diplexers in connection with small frequency-shift keying of gyrotrons can be used to switch the millimeter-wave power between two output channels. This technique can, for example, be used for fast beam steering for synchronous stabilization of rotating neoclassical tearing modes in tokamaks. Beam steering can be performed by a multistage multiplexer, provided that phase-controlled sources are available. In the paper, various concepts for fast directional switches as well as their integration into transmission lines are discussed. Calculations and low-power measurements of prototypes are presented. A resonant diplexer experiment is at present being prepared to be tested at high power in the electron cyclotron resonance heating (ECRH) system for Wendelstein 7X (W7-X). Requirements and techniques for frequency control of the gyrotrons are discussed, and the results of preliminary frequency modulation experiments are shown. Finally, future prospects for the application of diplexers in large ECRH systems are discussed.

/pdf/fast-switching-and-power-combination-of-high-power-electron-xfu2l2krjb.pdf

Fast switching and power combination of high-power electron cyclotron wave beams: principles, numerical results and experiments

For the upper electron cyclotron wave launcher on the international thermonuclear experimental reactor (ITER), the use of a 'remote steering antenna' based on the imaging properties of square waveguides is planned. To characterize launchers of this type, low-power experiments on a four-side corrugated square waveguide, with a scanning mirror at the input of the waveguide, were performed in the frequency range 140–160 GHz.It is shown that elliptical polarization, which is necessary for the electron cyclotron current drive (ECCD), can be transmitted without depolarization and that the usable steering range of the antenna is at least 20°.Low-power measurements demonstrate that mitre bends can be integrated into the waveguide, practically without extra loss. Detailed calorimetric measurements for this set-up confirm this statement for the polarization perpendicular to the scanning plane, whereas excess loss is measured for the parallel polarization. Various modifications of mitre bends are investigated and results are discussed.

Performance of a remote steering antenna for ECRH/ECCD applications

A method was developed to calculate the reflection of microwaves at corrugated metallic surfaces along with the expected ohmic losses and phase shifts. The implemented FDTD algorithm treats the wall as a plasma with a cutoff frequency far above the microwave frequency. This results in a self-consistent solution of the currents together with the E/M fields. After describing the algorithm, comparisons with loss and phase measurements are shown and an optimized corrugation profile is suggested.

Numerical Calculation of Reflection Characteristics of Grooved Surfaces with a 2D FDTD Algorithm

The stellarator W7-X, which is currently under construction at IPP Greifswald, Germany, will be equipped with a 10 MW ECRH system working at 140 GHz in CW regime. The microwave power will be generated by 10 gyrotrons delivering 1 MW each and will be transmitted from the gyrotron hall to the W7-X stellarator ports via a fully optical system. The status of the construction of the transmission lines and the design of the launchers is reported. Low-power tests of a prototype system at IPF Stuttgart are reviewed. Now, the first two gyrotrons are operating at IPP Greifswald, and high-power long-pulse tests have started. Measurements on transmission performance, behaviour of the water-cooled mirrors under thermal and microwave loads as well as alignment issues, characteristics of directional couplers, calorimetric loads, and other diagnostics are discussed.

Status of the 140 GHz, 10 MW CW transmission system for ECRH on the stellarator W7-X

Abs tract: Electron cyclotron heating (ECH) has proven to be one of the most attractive heating schemes for stellarators, as it provides net current free plasma start up and heating. Both, the stellarator Wendelstein 7-X (W7-X), which is under construction at IPP-Greifswald, Germany, and the ITER tokamak, which will be built at Cadarache, France, will be equipped with a strong EC-heating and current drive system. Both systems are comparable in frequency and have CW (continuous wave) capability (0.14 THz, 10 MW for W7-X and 0.17 THz, 24 MW for ITER). The commissioning of the ECH plant for W7-X is well underway, the status of the project and first integrated full power test results from two modules are reported and may provide valuable input for the ITER plant. The 10 gyrotrons at W7-X will be arranged in two sub-groups symmetrically to a central beam duct in the ECH hall. The RF-wave of each subgroup will be combined and transmitted by a purely optical multibeam wave guide transmission line (copper mirrors) from the gyrotrons to the plasma torus. The combination of the 5 gyrotron beams to two beam lines each with a power of 5 MW reduces the complexity of the system considerably. The single-beam as well as the multi-beam waveguide mirrors and the polarizers have been already manufactured. Cold tests of a full size uncooled prototype line delivered an efficiency exceeding 90%. The mm-wave power will be launched to the plasma through ten synthetic-diamond barrier windows and in-vessel quasi-optical plug-in launchers allowing each 1 MW RF-beam to be steered independently. The polarization as well as the poloidal and toroidal launch angle will be adjusted individually to provide optimum conditions for different heating and current drive scenarios. The first series gyrotrons were tested and yielded a total output power of 0.98 MW, with an efficiency of 31% (without a single-stage depressed collector) in short-pulse operation and of 0.92 MW in pulses of 1800 s (efficiency of almost 45% at a depression voltage of 29 kV). The Gaussian mode output power was 0.90 MW and the power measured in a calorimetric load after a 25-m-long quasi-optical transmission line (seven mirrors) was 0.87 MW.

/pdf/10-mw-0-14-thz-cw-gyrotron-and-optical-transmission-system-4dtfh88wxd.pdf

10 MW , 0.14 THz, CW Gyrotron and Optical Transmission System for Millimeter Wave Heating of Plasmas in the Stellarator W7-X

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Performance of a remote steering antenna for ECRH/ECCD applications

Status of the 140 GHz, 10 MW CW transmission system for ECRH on the stellarator W7-X

10 MW , 0.14 THz, CW Gyrotron and Optical Transmission System for Millimeter Wave Heating of Plasmas in the Stellarator W7-X