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100 1 _ |a Bernard, E.
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245 _ _ |a Tritium retention in W plasma-facing materials: Impact of the material structure and helium irradiation
260 _ _ |a Amsterdam [u.a.]
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520 _ _ |a 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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700 1 _ |a Sakamoto, R.
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700 1 _ |a Hodille, E.
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700 1 _ |a Kreter, A.
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700 1 _ |a Autissier, E.
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700 1 _ |a Barthe, M.-F.
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700 1 _ |a Desgardin, P.
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700 1 _ |a Schwarz-Selinger, T.
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700 1 _ |a Burwitz, V.
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700 1 _ |a Feuillastre, S.
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700 1 _ |a Garcia-Argote, S.
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700 1 _ |a Pieters, G.
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700 1 _ |a Rousseau, B.
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700 1 _ |a Ialovega, M.
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700 1 _ |a Bisson, R.
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700 1 _ |a Ghiorghiu, F.
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700 1 _ |a Corr, C.
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700 1 _ |a Thompson, M.
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700 1 _ |a Doerner, R.
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700 1 _ |a Markelj, S.
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700 1 _ |a Yamada, H.
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700 1 _ |a Yoshida, N.
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700 1 _ |a Grisolia, C.
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773 _ _ |a 10.1016/j.nme.2019.03.005
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