Home > Publications database > Tritium retention in W plasma-facing materials: Impact of the material structure and helium irradiation > print |
001 | 868241 | ||
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100 | 1 | _ | |a Bernard, E. |0 P:(DE-HGF)0 |b 0 |e Corresponding author |
245 | _ | _ | |a Tritium retention in W plasma-facing materials: Impact of the material structure and helium irradiation |
260 | _ | _ | |a Amsterdam [u.a.] |c 2019 |b Elsevier |
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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. |0 0000-0002-4453-953X |b 1 |
700 | 1 | _ | |a Hodille, E. |0 0000-0002-0859-390X |b 2 |
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700 | 1 | _ | |a Schwarz-Selinger, T. |0 P:(DE-HGF)0 |b 7 |
700 | 1 | _ | |a Burwitz, V. |0 0000-0002-9187-4867 |b 8 |
700 | 1 | _ | |a Feuillastre, S. |0 P:(DE-HGF)0 |b 9 |
700 | 1 | _ | |a Garcia-Argote, S. |0 P:(DE-HGF)0 |b 10 |
700 | 1 | _ | |a Pieters, G. |0 P:(DE-HGF)0 |b 11 |
700 | 1 | _ | |a Rousseau, B. |0 P:(DE-HGF)0 |b 12 |
700 | 1 | _ | |a Ialovega, M. |0 P:(DE-HGF)0 |b 13 |
700 | 1 | _ | |a Bisson, R. |0 0000-0002-8819-1563 |b 14 |
700 | 1 | _ | |a Ghiorghiu, F. |0 P:(DE-HGF)0 |b 15 |
700 | 1 | _ | |a Corr, C. |0 P:(DE-HGF)0 |b 16 |
700 | 1 | _ | |a Thompson, M. |0 P:(DE-HGF)0 |b 17 |
700 | 1 | _ | |a Doerner, R. |0 P:(DE-HGF)0 |b 18 |
700 | 1 | _ | |a Markelj, S. |0 P:(DE-HGF)0 |b 19 |
700 | 1 | _ | |a Yamada, H. |0 P:(DE-HGF)0 |b 20 |
700 | 1 | _ | |a Yoshida, N. |0 P:(DE-HGF)0 |b 21 |
700 | 1 | _ | |a Grisolia, C. |0 P:(DE-HGF)0 |b 22 |
773 | _ | _ | |a 10.1016/j.nme.2019.03.005 |g Vol. 19, p. 403 - 410 |0 PERI:(DE-600)2808888-8 |p 403 - 410 |t Nuclear materials and energy |v 19 |y 2019 |x 2352-1791 |
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