Study of deuterium retention in/release from ITER-relevant Be-containing mixed material layers implanted at elevated temperatures

Wall conditioning for ITER: Current experimental and modeling activities

“…It is reported in [13] that only about 50% of fuel implanted at 150°C can be released at 350°C, which may limit the efficiency of baking in this case. Significantly lower fuel content in co-deposited Be layers is however expected as the temperature at which co-deposits are formed is increased [13,14].…”

Effect of composition and surface characteristics on fuel retention in beryllium-containing co-deposited layers

“…The observations call for understanding how fuel is accumulating in co-deposits, and this is best met by systematic production of laboratory samples whose properties can be tailored over a wide range of parameters. Such layers have already been produced for plasma experiments in laboratories [8,9] and in linear plasma devices, most noticeably in PISCES-B [10][11][12][13][14]. Several trends for the dependence of retention on, e.g., the properties of the incoming plasma and the sample material have been reported but identifying how fuel is retained in a growing layer has attracted less attention.…”

Temperature influence on deuterium retention for Be–W mixed thin films prepared by Thermionic Vacuum Arc method exposed to PISCES B plasma

“…Due to the high density plasma conditions in a fusion reactor, material migration is likely to generate Be-W mixed surfaces. These mixed surfaces can influence fuel retention and desorption from the initial plasma-facing components, which in turn will affect the hydrogen recycling and in-vessel tritium inventory [2][3]. Examining the morphological and structural changes of the plasma facing materials, as well as fuel retention and release from such mixed material surfaces, as a function of exposing temperature was one of the aims of this work.…”