TY  - JOUR
AU  - Bernard, E.
AU  - Sakamoto, R.
AU  - Hodille, E.
AU  - Kreter, A.
AU  - Autissier, E.
AU  - Barthe, M.-F.
AU  - Desgardin, P.
AU  - Schwarz-Selinger, T.
AU  - Burwitz, V.
AU  - Feuillastre, S.
AU  - Garcia-Argote, S.
AU  - Pieters, G.
AU  - Rousseau, B.
AU  - Ialovega, M.
AU  - Bisson, R.
AU  - Ghiorghiu, F.
AU  - Corr, C.
AU  - Thompson, M.
AU  - Doerner, R.
AU  - Markelj, S.
AU  - Yamada, H.
AU  - Yoshida, N.
AU  - Grisolia, C.
TI  - Tritium retention in W plasma-facing materials: Impact of the material structure and helium irradiation
JO  - Nuclear materials and energy
VL  - 19
SN  - 2352-1791
CY  - Amsterdam [u.a.]
PB  - Elsevier
M1  - FZJ-2019-06801
SP  - 403 - 410
PY  - 2019
AB  - 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.
LB  - PUB:(DE-HGF)16
UR  - <Go to ISI:>//WOS:000470746100064
DO  - DOI:10.1016/j.nme.2019.03.005
UR  - https://juser.fz-juelich.de/record/868241
ER  -