Zobrazeno 1 - 8
of 8
pro vyhledávání: '"Cyril Patricot"'
Publikováno v:
EPJ Web of Conferences, Vol 247, p 07013 (2021)
Due to the high confinement of the closed fuel assemblies in Sodium-cooled Fast Reactors (SFR), the liquid sodium filling the space between these assemblies may vaporize in case of an important mechanical excitation (cavitation process). That phenome
Externí odkaz:
https://doaj.org/article/3c7fe61ebae24e8fa421f35fc6b26e60
Publikováno v:
Annals Nucl.Energy
Annals Nucl.Energy, 2021, 151, pp.107892. ⟨10.1016/j.anucene.2020.107892⟩
Annals of Nuclear Energy
Annals of Nuclear Energy, 2021, 151, pp.107892. ⟨10.1016/j.anucene.2020.107892⟩
Annals Nucl.Energy, 2021, 151, pp.107892. ⟨10.1016/j.anucene.2020.107892⟩
Annals of Nuclear Energy
Annals of Nuclear Energy, 2021, 151, pp.107892. ⟨10.1016/j.anucene.2020.107892⟩
International audience; This paper deals with the numerical optimization of a multiphysics calculation scheme. The purpose of this tool is the fine-scale neutronic and thermal-hydraulic modelling of Pressurized Water Reactors (PWRs), under steady-sta
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::83b08d3655272bdb7bf9edd8247275ef
https://hal.archives-ouvertes.fr/hal-03115775
https://hal.archives-ouvertes.fr/hal-03115775
Publikováno v:
Proceedings of the PHYSOR 2020, Cambridge, United Kingdom
PHYSOR 2020 Transition to a scalable nuclear future
PHYSOR 2020 Transition to a scalable nuclear future, Mar 2020, Cambridge, United Kingdom. 8 p
EPJ Web Conf.
International Conference on Physics of Reactors 2020: Transition to a Scalable Nuclear Future
International Conference on Physics of Reactors 2020: Transition to a Scalable Nuclear Future, Mar 2020, Cambridge, United Kingdom. pp.06008, ⟨10.1051/epjconf/202124706008⟩
EPJ Web of Conferences, Vol 247, p 06008 (2021)
PHYSOR 2020 Transition to a scalable nuclear future
PHYSOR 2020 Transition to a scalable nuclear future, Mar 2020, Cambridge, United Kingdom. 8 p
EPJ Web Conf.
International Conference on Physics of Reactors 2020: Transition to a Scalable Nuclear Future
International Conference on Physics of Reactors 2020: Transition to a Scalable Nuclear Future, Mar 2020, Cambridge, United Kingdom. pp.06008, ⟨10.1051/epjconf/202124706008⟩
EPJ Web of Conferences, Vol 247, p 06008 (2021)
ISBN 978-1-5272-6447-2; International audience; This work concerns the numerical optimization of a multiphysics calculation scheme. The considered application is a 5x5 Pressurized Water Reactor (PWR) assemblies mini-core surrounded by radial and axia
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::747398179ba64818ceb6928ef282e155
https://hal-cea.archives-ouvertes.fr/cea-02974036/file/PHYSOR2020-ID-1177.pdf
https://hal-cea.archives-ouvertes.fr/cea-02974036/file/PHYSOR2020-ID-1177.pdf
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2017, 101, pp.226-236. ⟨10.1016/j.anucene.2016.11.016⟩
Annals of Nuclear Energy, 2017, 101, pp.226-236. ⟨10.1016/j.anucene.2016.11.016⟩
Annals of Nuclear Energy, Elsevier Masson, 2017, 101, pp.226-236. ⟨10.1016/j.anucene.2016.11.016⟩
Annals of Nuclear Energy, 2017, 101, pp.226-236. ⟨10.1016/j.anucene.2016.11.016⟩
In this paper we focus on of Sodium Fast Reactor core undergoing several mechanical scenarios. The mechanical full-core model in Cast3M code is described using finite elements method and Fluid-Structure Interaction is taken into account. We consider
Publikováno v:
EPJ Web of Conferences; 2021, Vol. 247, p1-8, 8p
Publikováno v:
Progress in Nuclear Energy
Progress in Nuclear Energy, 2017, 101, pp.352-359. ⟨10.1016/j.pnucene.2017.03.021⟩
Progress in Nuclear Energy, Elsevier, 2017, 101, pp.352-359. ⟨10.1016/j.pnucene.2017.03.021⟩
Progress in Nuclear Energy, 2017, 101, pp.352-359. ⟨10.1016/j.pnucene.2017.03.021⟩
Progress in Nuclear Energy, Elsevier, 2017, 101, pp.352-359. ⟨10.1016/j.pnucene.2017.03.021⟩
International audience; The quasi-static method is widely used for space- and time-dependent neutron transport problems. It is based on the factorization of the flux into the product of two functions, an “amplitude” depending only on time and a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::61c354cfe82617f143326f8050ad16e4
https://hal.science/hal-03007066
https://hal.science/hal-03007066
Publikováno v:
EPJ Nuclear Sciences & Technologies, Vol 2, p 2 (2016)
EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, 2016, 2, pp.2. ⟨10.1051/epjn/e2015-50036-x⟩
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2016, 2, pp.2. ⟨10.1051/epjn/e2015-50036-x⟩
EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, 2016, 2, pp.2. ⟨10.1051/epjn/e2015-50036-x⟩
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2016, 2, pp.2. ⟨10.1051/epjn/e2015-50036-x⟩
In the frame of ASTRID designing, unprotected loss of flow (ULOF) accidents are considered. As the reactor is not scrammed, power evolution is driven by neutronic feedbacks, among which Doppler effect, linked to fuel temperature, is prominent. Fuel t
Publikováno v:
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo.