Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

By G. Federici, C. Skinner, J. Brooks, J. P. Coad, C. Grisolia, A. A. Haasz, A. Hassanein, V. Philipps, C. Pitcher, J. Roth and 2 more. 2001

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European DEMO design strategy and consequences for materials (2017, background): “In all current fusion device designs the power that crosses the magnetic separatrix (the last closed magnetic flux surface) is diverted along the magnetic field line to a remote region (the divertor) where it is exhausted on actively cooled divertor targets (see figure 11 below from [51]).”
Ultrafine tungsten as a plasma-facing component in fusion devices: effect of high flux, high fluence low energy helium irradiation (2014, background): “Low-Z films on tungsten [14, 15], tungsten composites and alloys [16] are currently some emergent plasma-facing component (PFC) designs, which require additional doping or deposited element(s) to tungsten.”
Physics of ultimate detachment of a tokamak divertor plasma (2017, methodology): “…modified due to the processes of erosion/re-deposition of the PFC material, implantation and desorption of the hydrogenic species, helium (which is inherent in the burning fusion plasmas) and impurities deliberately injected into the plasma for different purposes (see e.g. Federici et al. 2001).”
Loop and void damage during heavy ion irradiation on nanocrystalline and coarse grained tungsten: Microstructure, effect of dpa rate, temperature, and grain size (2018, background): “Tungsten is considered to be the primary choice as a plasma material interface (PMI) in fusion reactors [1].”