Zobrazeno 1 - 10
of 25
pro vyhledávání: '"Leturcq Bertrand"'
Autor:
Leturcq, Bertrand, Le Tallec, Patrick
Publikováno v:
Comptes Rendus. Mécanique, Vol , Iss , Pp 1-17 (2023)
The numerical simulation of multiscale and multiphysics problems requires efficient tools for spatial localization and model reduction. A general strategy combining Domain Decomposition and Nonuniform Transformation Field Analysis (NTFA) is proposed
Externí odkaz:
https://doaj.org/article/a2bd62cf542b4c3fb96e2e5ea49f1815
Autor:
de Lambert, Stanislas, Cardolaccia, Jérome, Faucher, Vincent, Leturcq, Bertrand, Campioni, Guillaume
Publikováno v:
In Progress in Nuclear Energy June 2023 160
Publikováno v:
In Nuclear Engineering and Design 1 August 2022 394
Autor:
de Lambert, Stanislas, Campioni, Guillaume, Faucher, Vincent, Leturcq, Bertrand, Cardolaccia, Jérome
Publikováno v:
In Annals of Nuclear Energy December 2019 134:330-341
Autor:
Leturcq, Bertrand
Publikováno v:
Sciences de l'ingénieur [physics]. école Polytechnique, 2022. Français. ⟨NNT : 2022IPPAX029⟩
Fuel assemblies deform progressively by a few millimeters within the core of pressurized water reactors. The main reasons are the hydraulic forces exerted by the coolant, the creep under irradiation and the contact-friction of the rods in the grids.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=od______3515::2dfc9c3751fc910fb06b364dfbdc5656
https://theses.hal.science/tel-03990361/document
https://theses.hal.science/tel-03990361/document
Publikováno v:
14th. Worl Congress on Computationnal Mechanics (WCCM 14)
14th. Worl Congress on Computationnal Mechanics (WCCM 14), Jan 2021, Paris, France
14th. Worl Congress on Computationnal Mechanics (WCCM 14), Jan 2021, Paris, France
International audience; Key Words: Model reduction, NTFA, Creep, Contact, Friction.Dealing with dimensional stability in nuclear industry often leads to consider irradiationcreeping as well as contact and friction. However, large detailed models requ
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3cec6a0fdd12f6bb770af444167fffdc
https://hal.archives-ouvertes.fr/hal-03202024
https://hal.archives-ouvertes.fr/hal-03202024
Akademický článek
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Publikováno v:
SMIRT-25-25th International Conference on STRUCTURAL MECHANICS in REACTOR TECHNOLOGY
SMIRT-25-25th International Conference on STRUCTURAL MECHANICS in REACTOR TECHNOLOGY, Aug 2019, Charlotte, United States
SMIRT-25-25th International Conference on STRUCTURAL MECHANICS in REACTOR TECHNOLOGY, Aug 2019, Charlotte, United States
International audience; In the pressure vessel of a PWR, the core is filled of up to 241 fuel assemblies. Under operation, they are subjected to irradiation growth, creeping, tightening relaxation and rod slipping. Combined with the hydraulic forces
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::6979906dc4a600b59bd0f290767510c3
https://hal-cea.archives-ouvertes.fr/cea-02478398/document
https://hal-cea.archives-ouvertes.fr/cea-02478398/document
Publikováno v:
CSMA 2019-14ème Colloque National en Calcul des Structures
CSMA 2019-14ème Colloque National en Calcul des Structures, May 2019, Giens, France
CSMA 2019-14ème Colloque National en Calcul des Structures, May 2019, Giens, France
International audience; On s'intéresse ici à la modélisation de la tenue du faisceau d'aiguilles des assemblages combustibles des réacteurs à neutrons rapides. Soumis à plusieurs phénomènes couplant neutronique, thermohydraulique, mécanique
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::9a697d16cf8c2ce9a10b3a8c143215a8
https://cea.hal.science/cea-02478418
https://cea.hal.science/cea-02478418