Zobrazeno 1 - 10
of 72
pro vyhledávání: '"A. S. Guilbert"'
Publikováno v:
Water Science and Technology, Vol 83, Iss 3, Pp 631-640 (2021)
Most cities face the problem of an aging infrastructure in need of extensive and ongoing repair, renovation or replacement. Since the 1980s, CCTV has been the industry standard for sewer system inspection and the main source of information for struct
Externí odkaz:
https://doaj.org/article/716c90753d6447f9a91e362a9fe7be6a
Autor:
M. Feyeux, L. Cordero-Espinoza, L. Milvoy, P. Morand, C. Morel, M. Abarkan, M. Husson, E. Luquet, M. Lanero Fidalgo, M. De Marco, L. Poincot, A. Jonckeau, E. Jamet, M. Cesari, H. Wurtz, J. Pletenka, L. Miternique, K. Moisan, L. Manache-Alberici, L. Piouceau, S. Guilbert, B. Gurchenkov, M. Lepleux, T. Dufourd, N. Prudon, V. Moutier, F. Moncaubeig, E. Faggiani
Publikováno v:
Cytotherapy. 25:S277
Publikováno v:
Water Science and Technology, Vol 83, Iss 3, Pp 631-640 (2021)
Most cities face the problem of an aging infrastructure in need of extensive and ongoing repair, renovation or replacement. Since the 1980s, CCTV has been the industry standard for sewer system inspection and the main source of information for struct
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2021, 548, pp.1-15. ⟨10.1016/j.jnucmat.2021.152854⟩
Journal of Nuclear Materials, Elsevier, 2021, 548, pp.1-15. ⟨10.1016/j.jnucmat.2021.152854⟩
International audience; An experimental study has been carried out on the high temperature oxidation behavior of pre-oxidized Zircaloy-4. Prior to steam oxidation, cladding tubes have been pre-oxidized in moistened oxygen environment at 425°C, up to
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2754860645cc27a1ac81326757844b73
https://hal.archives-ouvertes.fr/hal-03194902/document
https://hal.archives-ouvertes.fr/hal-03194902/document
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2021, 543, pp.152559. ⟨10.1016/j.jnucmat.2020.152559⟩
Journal of Nuclear Materials, Elsevier, 2021, 543, pp.152559. ⟨10.1016/j.jnucmat.2020.152559⟩
International audience; The influence of the nuclear fuel cladding pre-oxidation on post-LOCA quench resistance was experimentally studied and then modeled. Adopting a separate effect approach, quenched high temperature oxidized samples were axially
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::0b2845c2c94a76a1d8d47c1c71c57f62
https://hal.archives-ouvertes.fr/hal-03371773/file/0000167336_001.PDF
https://hal.archives-ouvertes.fr/hal-03371773/file/0000167336_001.PDF
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2021, 550, pp.1-14. ⟨10.1016/j.jnucmat.2021.152901⟩
Journal of nuclear materials, 550, Art.Nr. 152901
Journal of Nuclear Materials, Elsevier, 2021, 550, pp.1-14. ⟨10.1016/j.jnucmat.2021.152901⟩
Journal of nuclear materials, 550, Art.Nr. 152901
International audience; To assess the potential impact of using hafnium as absorber material in LWRs in high temperature accidental situations, the oxidation behavior of hafnium was studied up to 1400 °C, at temperature conditions relevant to severe
Publikováno v:
Engineering Fracture Mechanics
Engineering Fracture Mechanics, 2018, 193, pp.96-107. ⟨10.1016/j.engfracmech.2018.03.005⟩
Engineering Fracture Mechanics, 2018, 193, pp.96-107. ⟨10.1016/j.engfracmech.2018.03.005⟩
International audience; This paper investigates the room temperature cladding embrittlement of Stress Relieved Annealed (SRA) Zircaloy-4 fuel cladding samples subjected to laboratory steam oxidation tests simulating Loss of Coolant Accident (LOCA) tr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::28908cde94753117790d3c1d8dc81318
https://hal.archives-ouvertes.fr/hal-02871789
https://hal.archives-ouvertes.fr/hal-02871789
Autor:
S. Guilbert, Antoine Ambard, Marie-Christine Baietto, Martine Blat, Jean Desquines, Elodie Torres, Michel Coret, Pauline Lacote
Publikováno v:
EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2017, 3, ⟨10.1051/epjn/2017020⟩
EPJ Nuclear Sciences & Technologies, Vol 3, p 27 (2017)
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2017, 3, ⟨10.1051/epjn/2017020⟩
EPJ Nuclear Sciences & Technologies, Vol 3, p 27 (2017)
International audience; Oxygen and hydrogen distributions are key elements influencing the residual ductility of zirconium-based nuclear fuel cladding during the quench phase following a Loss Of Coolant Accident (LOCA). During the high temperature ox
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::1573820a48e0f05b2a682e03ae4759a8
https://hal.archives-ouvertes.fr/hal-01951563/document
https://hal.archives-ouvertes.fr/hal-01951563/document
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.