Zobrazeno 1 - 10
of 11
pro vyhledávání: '"Anne-Marie Baudron"'
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:
Transport Theory and Statistical Physics
Transport Theory and Statistical Physics, Taylor & Francis, 2012, 41, ⟨10.1080/00411450.2012.694827⟩
Transport Theory and Statistical Physics, 2012, 41, ⟨10.1080/00411450.2012.694827⟩
Transport Theory and Statistical Physics, Taylor & Francis, 2012, 41, ⟨10.1080/00411450.2012.694827⟩
Transport Theory and Statistical Physics, 2012, 41, ⟨10.1080/00411450.2012.694827⟩
International audience; In this article we present a domain decomposition method for the mixed SPN equations, discretized with Raviart-Thomas-Nédélec finite elements. This domain decomposition is based on the iterative Schwarz algorithm with Robin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9e21db59d63301d4b9e8f878aecac065
https://doi.org/10.1080/00411450.2012.694827
https://doi.org/10.1080/00411450.2012.694827
Publikováno v:
Mathematics and Computers in Simulation. 80:2159-2167
The neutronic simulation of a nuclear reactor core is performed using the neutron transport equation, and leads to an eigenvalue problem in the steady-state case. Among the deterministic resolution methods, simplified transport (SP"N) or diffusion ap
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5cdaa1fc6811fc062aed8ede2de654b2
https://doi.org/10.1016/j.matcom.2010.04.009
https://doi.org/10.1016/j.matcom.2010.04.009
Publikováno v:
Nuclear Science and Engineering
Nuclear Science and Engineering, 2007, 155 (2), pp.264-275. ⟨10.13182/NSE07-A2661⟩
Nuclear Science and Engineering, 2007, 155 (2), pp.264-275. ⟨10.13182/NSE07-A2661⟩
International audience; This paper describes a new technique for determining the pin power in heterogeneous 3D calculations. It is based on a domain decomposition with overlapping subdomains and a component mode synthesis technique for the global flu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::efb412485ceae519a088d4eabf315fa7
https://doi.org/10.13182/nse07-a2661
https://doi.org/10.13182/nse07-a2661
Publikováno v:
Nuclear Science and Engineering. 155:250-263
This paper describes a new generation of the neutronic core solver MINOS resulting from developments done in the DESCARTES project. For performance reasons, the numerical method of the existing MINOS solver in the SAPHYR system has been reused in the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1f6fb870042750903c36bdc3919f0f69
https://doi.org/10.13182/nse07-a2660
https://doi.org/10.13182/nse07-a2660
Publikováno v:
Journal of Computational Physics
Journal of Computational Physics, Elsevier, 2014, 279, pp.67-79. ⟨10.1016/j.jcp.2014.08.037⟩
Journal of Computational Physics, 2014, 279, pp.67-79. ⟨10.1016/j.jcp.2014.08.037⟩
Journal of Computational Physics, Elsevier, 2014, 279, pp.67-79. ⟨10.1016/j.jcp.2014.08.037⟩
Journal of Computational Physics, 2014, 279, pp.67-79. ⟨10.1016/j.jcp.2014.08.037⟩
International audience; Abstract In this paper we present a time-parallel algorithm for the 3D neutrons calculation of a transient model in a nuclear reactor core. The neutrons calculation consists in numerically solving the time dependent diffusion
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b7ebe1932e0ea0a82c2cf965cb251ec9
http://arxiv.org/abs/1403.1746
http://arxiv.org/abs/1403.1746
Publikováno v:
Lecture Notes in Computational Science and Engineering ISBN: 9783319057880
Studying numerically the steady state of a nuclear core reactor is expensive, in terms of memory storage and computational time. In order to address both requirements, one can use a domain decomposition method, implemented on a parallel computer. We
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8c0dc4fcc82fe97330053abdd633feee
https://doi.org/10.1007/978-3-319-05789-7_65
https://doi.org/10.1007/978-3-319-05789-7_65
Publikováno v:
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo.
The present paper deals with the resolution of the time-dependent neutron transport equation that is involved in the field of nuclear safety studies. Through the presentation of the newly implemented kinetic module in the MINARET solver [24] (develop
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1f930f64b851f5eaf84fb8938f332ec2
https://doi.org/10.1051/snamc/201404103
https://doi.org/10.1051/snamc/201404103
Publikováno v:
21st International Conference on Domain Decomposition Methods
21st International Conference on Domain Decomposition Methods, Jun 2012, Rennes, France
Lecture Notes in Computational Science and Engineering ISBN: 9783319057880
21st International Conference on Domain Decomposition Methods, Jun 2012, Rennes, France
Lecture Notes in Computational Science and Engineering ISBN: 9783319057880
International audience; In the framework of nuclear core calculations, the development of efficient tools to run neutron kinetic computations is a field of current active research. While such calculations are crucial for security assessment and the s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::484280220f9e527162a44c6b5ec39006
https://hal.sorbonne-universite.fr/hal-00908457/file/parareal_neutron_diffusion_MINOS_published.pdf
https://hal.sorbonne-universite.fr/hal-00908457/file/parareal_neutron_diffusion_MINOS_published.pdf
Publikováno v:
IPDPS Workshops
The third generation nuclear core should be attractive from the nuclear fuel cycle management aspect. The main goal is to achieve a good conversion of fertile isotopes into fissile isotopes while respecting safety constraints. Preliminary studies hav
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::29863a37198454aea025708eb17c55b5
https://doi.org/10.1109/ipdps.2011.175
https://doi.org/10.1109/ipdps.2011.175