Zobrazeno 1 - 10
of 10
pro vyhledávání: '"Daniele Sciannandrone"'
Publikováno v:
Annals of Nuclear Energy. 177:109301
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::63e3dc45beb3cf6cd55eb62dbf83f36f
https://doi.org/10.1016/j.anucene.2022.109301
https://doi.org/10.1016/j.anucene.2022.109301
Autor:
Matteo Falabino, Daniele Sciannandrone, Emiliano Masiello, Jean-François Vidal, Igor Zmijarevic
Publikováno v:
Journal of Computational Physics. 460:111156
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::46119ff872cf04aa2a96df3d68276026
https://doi.org/10.1016/j.jcp.2022.111156
https://doi.org/10.1016/j.jcp.2022.111156
Autor:
Matteo Falabino, Daniele Sciannandrone, Davide Mancusi, Emiliano Masiello, Andrea Zoia, Laurent Chabert, Odile Petit
Publikováno v:
The European Physical Journal Plus. 136
The solution of the Boltzmann equation for particle transport is the central problem of radiation shielding. When the solution is attempted using Monte Carlo methods, the use of variance reduction techniques is unavoidable, because the probability th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fb5ec18270a9536a976800126b51d6df
https://doi.org/10.1140/epjp/s13360-021-01594-7
https://doi.org/10.1140/epjp/s13360-021-01594-7
Publikováno v:
EPJ Web of Conferences, Vol 247, p 03004 (2021)
A new Discrete Ordinates transport solver for unstructured tetrahedral meshes is presented. The solver uses the Discontinuous Galërkin Finite Element Method with linear or quadratic expansion of the flux within each cell. The solution of the one-gro
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::438979bbe4bb4731c719c601b9ebb351
https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_03004.pdf
https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_03004.pdf
Publikováno v:
Annals of Nuclear Energy. 113:194-236
In recent years a solver based on the Method of Characteristics (MOC) allowing the treatment of 3D extruded geometries has been developed inside the TDT code of APOLLO3. The standard Step Characteristics (SC) approximation is used and results show an
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6160cb16593883900fcff229edc59963
https://doi.org/10.1016/j.anucene.2017.11.010
https://doi.org/10.1016/j.anucene.2017.11.010
Autor:
Eric Dumonteil, Davide Mancusi, H. Louvin, Michel Nowak, Daniele Sciannandrone, Emiliano Masiello
Publikováno v:
Nuclear Science and Engineering
Nuclear Science and Engineering, 2019, 193 (9), pp.966-981. ⟨10.1080/00295639.2019.1578568⟩
Nuclear Science and Engineering, 2019, 193 (9), pp.966-981. ⟨10.1080/00295639.2019.1578568⟩
In radiation protection studies, the goal is to estimate the response of a detector exposed to a strongly attenuated radiation field. Monte Carlo (MC) particle transport codes give the possibility to efficiently solve for such responses using several
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ca54e901da5b9c5e3333921f427e9102
https://hal.archives-ouvertes.fr/hal-03149128
https://hal.archives-ouvertes.fr/hal-03149128
Publikováno v:
Nuclear Science and Engineering
Nuclear Science and Engineering, 2017, 186 (3), pp.239-276. ⟨10.1080/00295639.2016.1273634⟩
Nuclear Science and Engineering, 2017, 186 (3), pp.239-276. ⟨10.1080/00295639.2016.1273634⟩
International audience; In this paper we describe some recent developments in the Method of Characteristics (MOC) for three-dimensional (3D) extruded geometries in the nuclear reactor analysis code APOLLO3®. We discuss the parallel strategies implem
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::eb151db04f04dd93d72e5c6de7a3ca89
https://cea.hal.science/cea-02381240
https://cea.hal.science/cea-02381240
Publikováno v:
EPJ Web Conf.
13th International Conference on Radiation Shielding (ICRS-13) & 19th Topical Meeting of the Radiation Protection & Shielding Division of the American Nuclear Society-2016 (RPSD-2016)
13th International Conference on Radiation Shielding (ICRS-13) & 19th Topical Meeting of the Radiation Protection & Shielding Division of the American Nuclear Society-2016 (RPSD-2016), Oct 2016, Paris, France. pp.06027, ⟨10.1051/epjconf/201715306027⟩
EPJ Web of Conferences, Vol 153, p 06027 (2017)
13th International Conference on Radiation Shielding (ICRS-13) & 19th Topical Meeting of the Radiation Protection & Shielding Division of the American Nuclear Society-2016 (RPSD-2016)
13th International Conference on Radiation Shielding (ICRS-13) & 19th Topical Meeting of the Radiation Protection & Shielding Division of the American Nuclear Society-2016 (RPSD-2016), Oct 2016, Paris, France. pp.06027, ⟨10.1051/epjconf/201715306027⟩
EPJ Web of Conferences, Vol 153, p 06027 (2017)
International audience; Recently a solver based on the Method Of Characteristics (MOC) for 3D extruded geometries has been developed in the APOLLO3® project [1]. In this method the domain is divided in regions and the Step Characteristics (SC) appro
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a407a78aa5775bdbd278ef62c58a583e
https://hal.archives-ouvertes.fr/hal-01645316
https://hal.archives-ouvertes.fr/hal-01645316
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2016, 87, pp.49-60. ⟨10.1016/j.anucene.2015.05.014⟩
Annals of Nuclear Energy, 2016, 87, pp.49-60. ⟨10.1016/j.anucene.2015.05.014⟩
Annals of Nuclear Energy, Elsevier Masson, 2016, 87, pp.49-60. ⟨10.1016/j.anucene.2015.05.014⟩
Annals of Nuclear Energy, 2016, 87, pp.49-60. ⟨10.1016/j.anucene.2015.05.014⟩
Specialized tracking techniques have been developed for a step-characteristics transport solver. These techniques strongly exploit the regularities of extruded 3D axial geometries to reduce the number of operations and the memory requirements of the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::401500b5e67c86d646785b8a4ae7bc3c
https://hal-cea.archives-ouvertes.fr/cea-03189927
https://hal-cea.archives-ouvertes.fr/cea-03189927
Publikováno v:
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo.
The solution of the neutron transport equation in 3D domains is a high resource demanding task. One of the most successful method of solution of this equation is the Method of Characteristics (MOC). However, the huge number of trajectories constitute
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a8fecad13289f54d146e11f2436ae2d8
https://doi.org/10.1051/snamc/201402209
https://doi.org/10.1051/snamc/201402209