Abstract
In toroidal magnetic fusion devices, fast-ion D-alpha diagnostic (FIDA) is a powerful method to study the fast-ion feature. The fast-ion characteristics can be inferred from the Doppler shifted spectrum of Dα light according to charge exchange recombination process between fast ions and probe beam. Since conceptual design presented in the last HTPD conference, significant progress has been made to apply FIDA systems on the Experimental Advanced Superconducting Tokamak (EAST). Both co-current and counter-current neutral beam injectors are available, and each can deliver 2-4 MW beam power with 50-80 keV beam energy. Presently, two sets of high throughput spectrometer systems have been installed on EAST, allowing to capture passing and trapped fast-ion characteristics simultaneously, using Kaiser HoloSpec transmission grating spectrometer and Bunkoukeiki FLP-200 volume phase holographic spectrometer coupled with Princeton Instruments ProEM 1024B eXcelon and Andor DU-888 iXon3 1024 CCD camera, respectively. This paper will present the details of the hardware descriptions and experimental spectrum.
Highlights
Fast ions in toroidal magnetic fusion devices are produced by fusion reactions, neutral beam injection (NBI), and ion cyclotron acceleration
Auxiliary heating systems on Experimental Advanced Superconducting Tokamak (EAST) have been improved and upgraded: both co-current and counter-current neutral beam injectors (NBIs) are available, and each can deliver 2-4 MW beam power with 50-80 keV beam energy; the lower hybrid current drive (LHCD) systems have been upgraded to 2.45 GHz/4 MW and 4.6 GHz/6 MW; and the total power of ion-cyclotron resonance heating (ICRH) systems can be up to 12 MW
Since conceptual design presented in the last HTPD conference,8 significant progress has been made to improve the capability and stability of fast-ion D-alpha diagnostic (FIDA) systems on EAST
Summary
Fast ions in toroidal magnetic fusion devices are produced by fusion reactions, neutral beam injection (NBI), and ion cyclotron acceleration They can be a major source of plasma heating and current drive. Auxiliary heating systems on EAST have been improved and upgraded: both co-current and counter-current neutral beam injectors (NBIs) are available, and each can deliver 2-4 MW beam power with 50-80 keV beam energy; the lower hybrid current drive (LHCD) systems have been upgraded to 2.45 GHz/4 MW and 4.6 GHz/6 MW; and the total power of ion-cyclotron resonance heating (ICRH) systems can be up to 12 MW
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