Corrigendum to 'Tritium retention in w plasma-facing materials: Impact of the material structure and helium irradiation' [Nucl. Mater. Energy 2019; 19: 403–410], Nuclear Materials and Energy, 22, 100729 (2020)

Autor: Ryuichi Sakamoto, Hiroshi Yamada, Matt Thompson, S. Garcia-Argote, V. V. Burwitz, Nobuaki Yoshida, E. Autissier, Marie-France Barthe, Etienne Hodille, R.P. Doerner, Sabina Markelj, Grégory Pieters, F Ghiorghiu, Régis Bisson, Pierre Desgardin, Thomas Schwarz-Selinger, B. Rousseau, Cormac Corr, Christian Grisolia, E. Bernard, Arkadi Kreter, S. Feuillastre, Mykola Ialovega

Publikováno v: Nuclear materials and energy 19, 403-410 (2019). doi:10.1016/j.nme.2019.03.005
Nuclear Materials and Energy
Nuclear Materials and Energy, 2019, 19, pp.403-410. ⟨10.1016/j.nme.2019.03.005⟩
Nuclear Materials and Energy, Vol 19, Iss, Pp 403-410 (2019)
Nuclear Materials and Energy, Elsevier, 2019, 19, pp.403-410. ⟨10.1016/j.nme.2019.03.005⟩

This article has an erratum: DOI 10.1016/j.nme.2020.100729 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 tri

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::1155f71d1165bc82497a557ec51bfcf5
https://juser.fz-juelich.de/record/868241

Three-dimensional scanning transmission electron microscopy of dislocation loops in tungsten

Autor: B. Décamps, Robin Schäublin, S. Hasanzadeh, V. Rousson, Marie-France Barthe, E. Autissier, Cécile Hébert

Publikováno v: Micron, 113
Micron
Micron, Elsevier, 2018, 113, pp.24-33. ⟨10.1016/j.micron.2018.05.010⟩

Scanning transmission electron microscopy (STEM) imaging using diffraction contrast is a powerful technique to assess crystal defects. In this work it is used to assess the spatial distribution of radiation induced defect in tungsten. In effect, its

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b8fda7cdd0a2ef0328613da01e7de98a
https://pubmed.ncbi.nlm.nih.gov/29945119

Operational limits on WEST inertial divertor sector during the early phase experiment

Autor: J. Y. Pascal, E. Autissier, M. Lipa, Marc Missirlian, D. Guilhem, H. Greuner, J. P. Gunn, P. Languille, C. Desgranges, C. Pocheau, Yann Corre, M. Firdaouss, M. Richou, E. Tsitrone

Publikováno v: Physica Scripta

The primary goal of the WEST project is to be a test bed to characterize the fatigue and lifetime of ITER-like W divertor components subjected to relevant thermal loads. During the first phase of exploitation (S2 2016), these components (W monoblock

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6a4dd6bf538e49fbc3b4e0069828de34
https://hdl.handle.net/11858/00-001M-0000-0029-5B54-611858/00-001M-0000-0029-5B52-A11858/00-001M-0000-002D-90A1-2

Design optimization of plasma facing component with functional gradient material Cu/W interlayer

Autor: M. Richou, M. Missirlian, E. Autissier, Frédéric Bernard

Publikováno v: Fusion Engineering and Design

In the current water cooled divertor concept, tungsten is an armor material and CuCrZr is a structural material. The difference in thermal expansion coefficient between tungsten and copper alloy causes a thermal mismatch between them resulting in acc

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::65abdec911f14328348397a23a13d255

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