Zobrazeno 1 - 10
of 117
pro vyhledávání: '"M.A. Auger"'
Autor:
M. Oñoro, E. Salas-Colera, S.R. Parnell, V. Martin-Diaconesu, D. Alba Venero, T. Leguey, V. de Castro, M.A. Auger
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101713- (2024)
In this work, Zr addition is proposed to refine the nanoparticle dispersion in an ODS RAF steel of composition Fe-14Cr-2W-0.3Zr-0.24Y (wt.%). Three batches of material are obtained using pre-alloyed atomized powder, where yttrium is directly introduc
Externí odkaz:
https://doaj.org/article/8648eca987d74fc4b4628bb989521eef
Autor:
M. Oñoro, S.R. Parnell, E. Salas-Colera, D. Alba Venero, V. Martin-Diaconesu, T. Leguey, V. de Castro, M.A. Auger
Publikováno v:
Nuclear Materials and Energy, Vol 39, Iss , Pp 101671- (2024)
An ODS steel with nominal composition Fe–14Cr–2W–0.4Ti-0.3Y2O3 (wt.%) was produced by mechanical alloying and compacted by hot isostatic pressing (HIP) followed by hot cross rolling (HCR). To check the effects of thermal aging at relevant tempe
Externí odkaz:
https://doaj.org/article/2a913a08072e4d41a89b5bb0b169122c
Publikováno v:
Nuclear Materials and Energy, Vol 36, Iss , Pp 101455- (2023)
This investigation presents the effects of long-term thermal aging on the impact properties of an ODS reduced activation ferritic steel. The ODS ferritic steel, with composition Fe–14Cr–2W–0.4Ti–0.3Y2O3 (wt. %), was manufactured by mechanical
Externí odkaz:
https://doaj.org/article/d87213b7fede4c5e882ff3498ade31e1
Autor:
M. Šćepanović, T. Leguey, I. García-Cortés, F.J. Sánchez, C. Hugenschmidt, M.A. Auger, V. de Castro
Publikováno v:
Nuclear Materials and Energy, Vol 25, Iss , Pp 100790- (2020)
Oxide dispersion strengthened steels are candidate materials for nuclear reactor applications due to a powerful combination of properties, such as reduced activation, high-temperature strength and increased creep resistance. The dispersion of nanomet
Externí odkaz:
https://doaj.org/article/a7ca59e1b5a74041ad6a59a12b6afc8c
Publikováno v:
Nuclear Materials and Energy, Vol 24, Iss , Pp 100758- (2020)
The thermal stability of an ODS RAF steel has been investigated by assessing the effects of different thermal treatments on its microstructure and mechanical behavior. The ODS steel, with nominal composition Fe–14Cr–2W–0.4Ti-0.3Y2O3 (wt. %), wa
Externí odkaz:
https://doaj.org/article/d3a213d89b4143f1a49fa772307cad08
Autor:
J. Macías-Delgado, T. Leguey, V. de Castro, M.A. Auger, M.A. Monge, P. Spätig, N. Baluc, R. Pareja
Publikováno v:
Nuclear Materials and Energy, Vol 9, Iss C, Pp 372-377 (2016)
An oxide dispersion strengthened ODS ferritic steel has been produced by mechanical alloying of Fe–14Cr–2W–0.2Ti (wt.%) prealloyed powder with 0.55 (wt.%) Fe2Y intermetallic particles and consolidated by hot isostatic pressing. The microstructu
Externí odkaz:
https://doaj.org/article/a79554c432f54a15a2d32d4d95341237
Publikováno v:
Nuclear Materials and Energy, Vol 9, Iss C, Pp 490-495 (2016)
Simultaneous triple-ion beam irradiation experiments with Fe5+, He+ and H+ ions were performed to simulate fusion damage on two nanostructured ferritic alloys with nominal composition Fe–14Cr–0.3Y2O3 and Fe–14Cr–2W–0.3Ti–0.3Y2O3. Samples
Externí odkaz:
https://doaj.org/article/0e02bde394154691a09e5ee2952da6a7
Akademický článek
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Akademický článek
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Autor:
M.A. Auger, Christina Hofer, Paul A. J. Bagot, David E.J. Armstrong, T. P. Davis, Michael P. Moody
Ion irradiation has been used to investigate the radiation-induced precipitation of nanoclusters and changes in mechanical properties of commercial-grade T91 ferritic-martensitic steel irradiated with Fe4+ ions up to 4.10 dpa at 301 – 311 °C. Atom
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::856575a39d3ea5940daff322bbf82b63
https://ora.ox.ac.uk/objects/uuid:65778962-6485-47ee-9548-c40049d5937e
https://ora.ox.ac.uk/objects/uuid:65778962-6485-47ee-9548-c40049d5937e
