Tritium retention in W plasma-facing materials: Impact of the material structure and helium irradiation

Bernard, E.; Barthe, M.-F.; Kreter, A.; Rousseau, B.; Sakamoto, R.; Ghiorghiu, F.; Schwarz-Selinger, T.; Hodille, E.; Autissier, E.; Yoshida, N.; Yamada, H.; Burwitz, V.; Pieters, G.; Doerner, R.; Bisson, R.; Thompson, M.; Feuillastre, S.; Garcia-Argote, S.; Corr, C.; Grisolia, C.; Ialovega, M.; Desgardin, P.; Markelj, S.

doi:10.1016/j.nme.2019.03.005

Journal Article

FZJ-2019-06801

Tritium retention in W plasma-facing materials: Impact of the material structure and helium irradiation

Bernard, E. (Corresponding author) ; Sakamoto, R. ; Hodille, E. ; Kreter, A.FZJ* ; Autissier, E. ; Barthe, M.-F. ; Desgardin, P. ; Schwarz-Selinger, T. ; Burwitz, V. ; Feuillastre, S. ; Garcia-Argote, S. ; Pieters, G. ; Rousseau, B. ; Ialovega, M. ; Bisson, R. ; Ghiorghiu, F. ; Corr, C. ; Thompson, M. ; Doerner, R. ; Markelj, S. ; Yamada, H. ; Yoshida, N. ; Grisolia, C.

2019
Elsevier Amsterdam [u.a.]

Nuclear materials and energy 19, 403 - 410 (2019) [10.1016/j.nme.2019.03.005]

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Please use a persistent id in citations: http://hdl.handle.net/2128/23720 doi:10.1016/j.nme.2019.03.005

Abstract: 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.

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