%0 Journal Article
%A Bernard, E.
%A Sakamoto, R.
%A Hodille, E.
%A Kreter, A.
%A Autissier, E.
%A Barthe, M.-F.
%A Desgardin, P.
%A Schwarz-Selinger, T.
%A Burwitz, V.
%A Feuillastre, S.
%A Garcia-Argote, S.
%A Pieters, G.
%A Rousseau, B.
%A Ialovega, M.
%A Bisson, R.
%A Ghiorghiu, F.
%A Corr, C.
%A Thompson, M.
%A Doerner, R.
%A Markelj, S.
%A Yamada, H.
%A Yoshida, N.
%A Grisolia, C.
%T Tritium retention in W plasma-facing materials: Impact of the material structure and helium irradiation
%J Nuclear materials and energy
%V 19
%@ 2352-1791
%C Amsterdam [u.a.]
%I Elsevier
%M FZJ-2019-06801
%P 403 - 410
%D 2019
%X Plasma-facing materials for next generation fusion devices, like ITER and DEMO, will be submitted to intense fluxes of light elements, notably He and H isotopes (HI). Our study focuses on tritium (T) retention on a wide range of W samples: first, different types of W materials were investigated to distinguish the impact of the pristine original structure on the retention, from W-coated samples to ITER-grade pure W samples submitted to various annealing and manufacturing procedures, along with monocrystalline W for reference. Then, He and He-D irradiated W samples were studied to investigate the impact on He-damages such as nano-bubbles (exposures in LHD or PSI-2) on T retention.
%F PUB:(DE-HGF)16
%9 Journal Article
%U <Go to ISI:>//WOS:000470746100064
%R 10.1016/j.nme.2019.03.005
%U https://juser.fz-juelich.de/record/868241