Three generations of plasma facing components (PFCs) have been used in Experimental Advanced Superconducting Tokamak (EAST): stainless steel for the initial campaign, fully actively cooled doped graphite PFC and a combination of a graphite divertor with a molybdenum first wall. The doped graphite with a ∼100 μ m-thick SiC coating has shown good performance for the past 5 years with a heat load removal capacity of 2 MW m −2 . An ITER-like W mono-block divertor and W flat-type tiles will be used in the second phase of EAST with long pulse operation beginning in 2013. A hot W wall over 350 °C will be used in the third phase of EAST operation from 2017 when nearly 40 MW of heating and current drive power will be utilized. Combining these experiences of PFCs together with divertor operation optimization, a solid technical basis will be established for the Chinese Fusion Engineering Testing Reactor.
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Li et al. (2014) studied this question.
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