Calculated Sputtering, Reflection and Range Values

By W. Eckstein. 2002

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Basic physical processes and reduced models for plasma detachment (2018, unknown): “Since the self-sputtering yield for W exceeds unity for impact energy 1 keV [25], in principle a self-sputtering cascade can occur; however, Chankin [28] has shown that this is very unlikely to occur for expected divertor conditions in ITER.”
Observations of suppressed retention and blistering for tungsten exposed to deuterium–helium mixture plasmas (2009, unknown): “Ion ranges of D and He in W as a function of ion energy [18].”
Fuel retention studies with the ITER-Like Wall in JET (2013, unknown): “laboratory studies [27], comparable erosion yields providing”
Tungsten ‘fuzz’ growth re-examined: the dependence on ion fluence in non-erosive and erosive helium plasma (2015, background): “Accordingly, if the yield is taken from measurements or predictions [24] of the sputter yield made for bulk tungsten (Ybulk), the porosity term cancels and fuzz = bulk, as was demonstrated recently in [7].”