Zobrazeno 1 - 5
of 5
pro vyhledávání: '"Pauline Lacote"'
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
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2016, 469, pp.20-31. ⟨10.1016/j.jnucmat.2015.11.008⟩
Journal of Nuclear Materials, Elsevier, 2016, 469, pp.20-31. ⟨10.1016/j.jnucmat.2015.11.008⟩
International audience; During a Loss Of Coolant Accident (LOCA), the mechanical behavior of high temperature steam oxidized fuel rods is an important issue. In this study, as-received and pre-hydrided axial tensile samples were steam oxidized in a v
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::caaf0114bef9c04da496552fee2c7b1e
https://hal.archives-ouvertes.fr/hal-02557552
https://hal.archives-ouvertes.fr/hal-02557552
Autor:
Gaëlle Taraud, Pauline Lacote, Christian Duriez, Jean Desquines, Pascal Berger, Séverine Guilbert-Banti
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2015, 469, pp.228-236. ⟨10.1016/j.jnucmat.2015.11.019⟩
Journal of Nuclear Materials, 2015, 469, pp.228-236. ⟨10.1016/j.jnucmat.2015.11.019⟩
Journal of Nuclear Materials, Elsevier, 2015, 469, pp.228-236. ⟨10.1016/j.jnucmat.2015.11.019⟩
Journal of Nuclear Materials, 2015, 469, pp.228-236. ⟨10.1016/j.jnucmat.2015.11.019⟩
International audience; Despite the influence of hydrogen on the behavior of zirconium fuel cladding in many nuclear safety issues, the pseudo-binary Zircaloy-4 e oxygen phase diagram still lacks of data, especially above 1000 C. The aim of this stud
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d2092354f3e9a9248930ce3aff157f25
https://hal-cea.archives-ouvertes.fr/cea-01261954
https://hal-cea.archives-ouvertes.fr/cea-01261954
Publikováno v:
EPJ Nuclear Sciences & Technologies, Vol 2, p 13 (2016)
During a Loss Of Coolant Accident (LOCA), an important safety requirement is that the reflooding of the core by the emergency core cooling system should not lead to a complete rupture of the fuel rods. Several types of mechanical tests are usually pe