The effect of discrete structures such as macrobrush or castellated surfaces on power handling and deuterium retention of plasma facing components is to be assessed since such geometrical configurations are needed for increasing the lifetime of the armour to heat-sink joint. Four small macrobrush W and W + 1%La2O3samples have been exposed in the Frascati Tokamak Upgrade (FTU) scrape-off layer up to the last closed flux surface by means of the Sample Introduction System. FTU is an all metal machine with no carbon source inside vacuum vessel; it exhibits ITER relevant energy and particle fluxes on the plasma facing components. Here, results on morphological surface changes (SEM), chemical composition (EDX) and deuterium retention (TDS) are reported. © 2007 Elsevier B.V. All rights reserved.
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Materials Science(all)
- Nuclear Energy and Engineering
Maddaluno, G., Giacomi, G., Rufoloni, A., & Verdini, L. (2007). Deuterium retention and surface modification of tungsten macrobrush samples exposed in FTU Tokamak. Journal of Nuclear Materials, 363-365(1-3), 1236 - 1240. https://doi.org/10.1016/j.jnucmat.2007.01.256