2018Unpublished venueRequires access

Modeling of ICRF Antenna Coupling on East Tokamak

Chunyun Gan, David Smithe, Nong Xiang, Xiniun Zhang

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Abstract

Radiofrequency wave in ion cyclotron range of frequency (ICRF) is an important way for heating plasma, driving current and implementing plasma control in the magnetic fusion devices such as EAST and ITER tokamak. Achieving good coupling of ICRF power into the plasma is an essential issue for high power ICRF injection on the EAST tokamak. In this work, the high-performance Finite-difference time-domain (FDTD) methods in VSim software1, 2have been carried out to model the realistic ICRF behavior, especially coupling on the EAST tokamak. The detailed 3D geometry of the I-port ICRF antenna module is built in the modeling. Plasma parameters are chosen to resemble those of the ICRF heating experiments on EAST tokamak3. Effects of the plasma density parameter and edge neutral gas on the ICRF coupling efficiency are presented.

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What this paper is about

Radiofrequency wave in ion cyclotron range of frequency (ICRF) is an important way for heating plasma, driving current and implementing plasma control in the magnetic fusion devices such as EAST and ITER tokamak. Achieving good coupling of ICRF power into the plasma is an essential issue for high power ICRF injection on the EAST tokamak. In this work, the high-performance Finite-difference time-domain (FDTD) methods in VSim software1, 2have been carried out to model the realistic ICRF behavior, especially coupling on the EAST tokamak. The detailed 3D geometry of the I-port ICRF antenna module is built in the modeling. Plasma parameters are chosen to resemble those of the ICRF heating experiments on EAST tokamak3. Effects of the plasma density parameter and edge neutral gas on the ICRF coupling efficiency are presented.

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Available abstract

Radiofrequency wave in ion cyclotron range of frequency (ICRF) is an important way for heating plasma, driving current and implementing plasma control in the magnetic fusion devices such as EAST and ITER tokamak. Achieving good coupling of ICRF power into the plasma is an essential issue for high power ICRF injection on the EAST tokamak. In this work, the high-performance Finite-difference time-domain (FDTD) methods in VSim software1, 2have been carried out to model the realistic ICRF behavior, especially coupling on the EAST tokamak. The detailed 3D geometry of the I-port ICRF antenna module is built in the modeling. Plasma parameters are chosen to resemble those of the ICRF heating experiments on EAST tokamak3. Effects of the plasma density parameter and edge neutral gas on the ICRF coupling efficiency are presented.

Key concepts: Tokamak, Coupling (piping), Plasma, Antenna (radio), Physics, Cyclotron, Computational physics, Atomic physics

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