Abstract
The key issue of burning plasma in tokamak is the loss and confinement of the energetic particles, and one of the loss channels is the perturbation due to discrete toroidal field coils. The work investigated the α ripple loss of CFETR hybrid scenario with plasma transportation code TRANSP/NUBEAM and guiding center code ORBIT, which have considered the initial α distribution, classical steady state slowing down distribution and other models. The results of the work can give the information of the lost particles, including the lost position, fraction and localized heat load on the wall. The study reveals the heat load on CFETR is about 0.13 MW/m2, which is below the safety threshold of ITER, 0.5 MW/m2, and the paper also gives the direction to reduce the α ripple loss.
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