Abstract
This study reports a prototype design of the front steerable mirror (SM) in the Electron Cyclotron Resonance Heating (ECRH) system, which is used to validate the manufacturing technology of the large-scale quasi-optical mirror in the China Fusion Engineering Test Reactor (CFETR). As a plasma-oriented component, the SM will experience more neutron heat and plasma radiation heat than the remote focusing mirrors, and the simulation results indicate that the peak temperature of the SM would then reach 292.5 °C, the maximum deformation and the maximum equivalent stress would be 1.16 mm and 446 MPa, respectively. The beam exhibits little distortion because the thermal deformation gradient around the wave center is small, and the quasi-optical analysis shows that the position of the wave heating plasma should be shifted by -6 mm along the local Z-axis, while the amplitude of the central electrical field would increase by 0.3%, from 294.7 kV/m to 295.5 kV/m.
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