Zobrazeno 1 - 10
of 40
pro vyhledávání: '"N. De Wispelaere"'
Autor:
Heiko Neuberger, Michael Rieth, Bradut-Eugen Ghidersa, Jörg Rey, E. Simondon, Michael Dürrschnabel, Giacomo Aiello, Simon Bonk, N. De Wispelaere, Christian Zeile, Y. de Carlan, J. Henry, Jan Hoffmann, Gerald Pintsuk
Publikováno v:
Fusion Engineering and Design
Fusion Engineering and Design, 2021, 166, pp.112275. ⟨10.1016/j.fusengdes.2021.112275⟩
Fusion engineering and design 166, 112275-(2021). doi:10.1016/j.fusengdes.2021.112275
Fusion Engineering and Design, 166, Art.-Nr.: 112275
Fusion Engineering and Design, 2021, 166, pp.112275. ⟨10.1016/j.fusengdes.2021.112275⟩
Fusion engineering and design 166, 112275-(2021). doi:10.1016/j.fusengdes.2021.112275
Fusion Engineering and Design, 166, Art.-Nr.: 112275
A major part in the EUROfusion materials research program is dedicated to characterize and quantify nuclear fusion specific neutron damage in structural materials. While the majority of irradiation data gives a relatively clear view on the displaceme
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::60110e5cb2a686ed3a6afeac9d670831
https://hal-cea.archives-ouvertes.fr/cea-03850184
https://hal-cea.archives-ouvertes.fr/cea-03850184
Autor:
Jan Hoffmann, N. De Wispelaere, Gerald Pintsuk, Michael Rieth, Y. de Carlan, J. Henry, Michael Dürrschnabel, Steffen Antusch, Christian Zeile, Jörg Rey, Bradut-Eugen Ghidersa, Heiko Neuberger, Giacomo Aiello, Simon Bonk, E. Simondon
Publikováno v:
Nuclear fusion 61(11), 116067-(2021). doi:10.1088/1741-4326/ac2523
Nuclear fusion, 61 (11), 116067
Nuclear fusion, 61 (11), 116067
In future nuclear fusion reactors, plasma facing components have to sustain specific neutron damage. While the majority of irradiation data provides a relatively clear picture of the displacement damage, the effect of helium transmutation is not yet
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::1d94c2fc34086c7b0a417e586bf6ed01
Publikováno v:
Journal of Nuclear Materials
The C, N, and W content in EUROFER97, a 9CrWVTa reduced-activation ferritic/martensitic (RAFM) steel, was varied to obtain an experimental assessment of the main effects of the compositional variation on the mechanical properties and microstructural
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::567bbe5c4b77676741104cdaa7d67a4f
https://doi.org/10.1016/j.jnucmat.2018.02.017
https://doi.org/10.1016/j.jnucmat.2018.02.017
Akademický článek
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Publikováno v:
Journal of Nuclear Materials, 494
Journal of Nuclear Materials
Journal of Nuclear Materials
The microstructure of a 9Cr-1W-0.22V-0.09Ta-0.11C reduced activation ferritic/martensitic (RAFM) steel has been investigated after thermo-mechanical rolling with subsequent annealing for 30 min at temperatures of 880 °C, 920 °C, 980 °C and 1050 °
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::41acf2b151b918da1844f855e9520be0
http://resolver.tudelft.nl/uuid:f663dd77-583f-4df0-8d6f-d9adc7127826
http://resolver.tudelft.nl/uuid:f663dd77-583f-4df0-8d6f-d9adc7127826
Autor:
A. De Bremaecker, N. De Wispelaere, K. Verbeken, Katelijne Verhiest, Steven Mullens, Serge Claessens, I. De Graeve
Publikováno v:
Ceramics International. 40:14319-14334
High-temperature creep and corrosion resistant nano-dispersed ferritic/martensitic (F/M) alloys (such as a T91 steel), or other ‘the oxide dispersion strengthened (ODS) steels’, are under consideration for nuclear applications because of their hi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eeb169d6da9ec77d4800165bde4fec93
https://doi.org/10.1016/j.ceramint.2014.06.023
https://doi.org/10.1016/j.ceramint.2014.06.023
Autor:
I. De Graeve, Serge Claessens, Katelijne Verhiest, Kim Verbeken, Steven Mullens, A. DeBremaecker, J. Paul, N. De Wispelaere
Publikováno v:
Ceramics International. 40:7679-7692
Oxide dispersion strengthened (ODS) steels are considered as the future structural material of interest for nuclear power plants, due to their elevated creep resistance at higher operation temperatures. In this study, a 0.3 wt% nano-yttria (Y 2 O 3 )
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ab19b05f15b299dfa605e010f52b09de
https://doi.org/10.1016/j.ceramint.2013.12.109
https://doi.org/10.1016/j.ceramint.2013.12.109
Autor:
Steven Mullens, I. De Graeve, N. De Wispelaere, Serge Claessens, Katelijne Verhiest, J. Paul, Kim Verbeken, A. DeBremaecker
Publikováno v:
Ceramics International. 40:2187-2200
High-temperature contact angle experiments of liquid iron–chromium (Fe–Cr) drops onto ceramic yttria (Y 2 O 3 ) substrates were carried out in order to investigate the wetting behavior of Y 2 O 3 nano-particles in contact with an iron melt contai
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eaa172cd39448cbd1ec859c63c0caa83
https://doi.org/10.1016/j.ceramint.2013.07.137
https://doi.org/10.1016/j.ceramint.2013.07.137
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.
Autor:
Kim Verbeken, Katelijne Verhiest, Serge Claessens, N. De Wispelaere, S Mullens, A. DeBremaecker
Publikováno v:
Journal of Nuclear Materials. 428:54-64
In this study, oxide dispersion strengthened (ODS) 316L steel samples were manufactured by the 3 dimensional fiber deposition (3DFD) technique. The performance of 3DFD as colloidal consolidation technique to obtain porous green bodies based on yttria
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::aecd9284b542fa01768f030c2971fe06
https://doi.org/10.1016/j.jnucmat.2012.01.025
https://doi.org/10.1016/j.jnucmat.2012.01.025