Overview of plasma-facing materials and components for EAST

Status and strategy of fusion materials development in China

“…tungsten, are increasingly considered as the primary candidate armor materials facing the plasma in tokamaks for medium to high heat flux components. Tungsten-based alloys are planned to be used as PFM in the long-term operation in EAST (Experimental Advanced Superconducting Tokamak) [30]. A new liquid diverter and liquid first wall concept has been put forward and study on its possibility for commercial pure fusion reactors is underway [29].…”

Characterization and erosion of metal-containing carbon films

“…The selection of dopants was driven by the material selection for ITER and the proposed use of doped graphites in present and future fusion devices, e.g., EAST [6,13]. Metal-doped carbon films deposited atomically by magnetron-sputtering appear to be the ideal model material for mechanistic investigations on the effect of doping on the erosion of carbon by hydrogen.…”

“…The planned use of Be, W, and C in ITER as well as the present use of Be and C in JET [3,4], of W and C in ASDEX Upgrade [5] and of Si-B-Ti-doped fine graphites in EAST [6] increase the interest on the erosion and hydrogen retention behaviour of mixed carbon-metal layers [7].…”

Tritium uptake in graphite tiles exposed to EAST plasma and then tritium gas

“…And the experiences on SiC will give great evidence for PWI on W-PFM. In our preliminary work, some basic properties of SiC coatings and behavior with exposure to HT-7 plasmas have been investigated [3,4], and the adsorption/retention of hydrogen isotopes had been investigated by ␤-ray-induced X-ray spectrometry (BIXS) comparing with doped graphite and W coatings fabricated by vacuum plasma spraying [5]. To better understand the behavior of the SiC/C-PFMs in different erosion/deposition areas in EAST, it is of great importance to accumulate the basic data such as the amount of adsorption and depth profiles of tritium in the PFMs.…”