Zobrazeno 1 - 10
of 12
pro vyhledávání: '"Cheikh M. Diop"'
Autor:
Emeric Brun, Cheikh M. Diop, Odile Petit, Fausto Malvagi, F. X. Hugot, J. C. Trama, Y. K. Lee, Andrea Zoia, Alain Mazzolo, Cédric Jouanne, T. Visonneau, Eric Dumonteil, Frédéric Damian
Publikováno v:
Annals of Nuclear Energy. 82:151-160
This paper presents an overview of TRIPOLI-4®, the fourth generation of the 3D continuous-energy Monte Carlo code developed by the Service d’Etudes des Réacteurs et de Mathématiques Appliquées (SERMA) at CEA Saclay. The paper surveys the generi
Publikováno v:
Annals of Nuclear Energy. 79:43-50
Monte-Carlo burnup calculations are nowadays the reference method to obtain fuel inventories in reactor configurations. Their main drawback is the very long computing time associated with the calculation. A method is presented here which attempts to
Publikováno v:
EPJ Web of Conferences
EPJ Web of Conferences, EDP Sciences, 2017, 153, pp.1-9. ⟨10.1051/epjconf/201715306006⟩
EPJ Nuclear Sciences & Technologies
EPJ Nuclear Sciences & Technologies, 2017, 3, pp.29. 〈10.1051/epjn/2017022〉
EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, 2017, 3, pp.29. ⟨10.1051/epjn/2017022⟩
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2017, 3, pp.29. ⟨10.1051/epjn/2017022⟩
EPJ Nuclear Sciences & Technologies, Vol 3, p 29 (2017)
EPJ Web of Conferences, Vol 153, p 06006 (2017)
EPJ Web of Conferences, EDP Sciences, 2017, 153, pp.1-9. ⟨10.1051/epjconf/201715306006⟩
EPJ Nuclear Sciences & Technologies
EPJ Nuclear Sciences & Technologies, 2017, 3, pp.29. 〈10.1051/epjn/2017022〉
EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, 2017, 3, pp.29. ⟨10.1051/epjn/2017022⟩
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2017, 3, pp.29. ⟨10.1051/epjn/2017022⟩
EPJ Nuclear Sciences & Technologies, Vol 3, p 29 (2017)
EPJ Web of Conferences, Vol 153, p 06006 (2017)
International audience In the Monte Carlo simulation of particle transport, and especially for shielding applications, variance reduction techniques are widely used to help simulate realisations of rare events and reduce the relative errors on the es
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5cc91d2dd4ee807734ae34b7018b460e
https://hal.archives-ouvertes.fr/hal-01661012
https://hal.archives-ouvertes.fr/hal-01661012
Autor:
Cheikh M. Diop, Christophe Calvin
Publikováno v:
Revue Générale Nucléaire. :41-48
Publikováno v:
EPJ Web of Conferences, Vol 106, p 05006 (2016)
ISRD 2014-15th International Symposium on Reactor Dosimetry
ISRD 2014-15th International Symposium on Reactor Dosimetry, May 2014, Aix en provence, France
ISRD 2014-15th International Symposium on Reactor Dosimetry
ISRD 2014-15th International Symposium on Reactor Dosimetry, May 2014, Aix en provence, France
International audience; In this paper we present a nuclear heating from neutron and photon rays calculation scheme mainly based on the Monte-Carlo neutral particle transport code TRIPOLI-4 ® which takes into account fuel elements axial distributions
Publikováno v:
Nuclear Science and Engineering. 170:87-97
In the frame of neutral-particle (neutron, gamma) transport, the uncertainty propagation calculation regarding the uncertainties on cross sections is often carried out without explicitly taking int...
Autor:
Cheikh M. Diop
Publikováno v:
Nuclear Science and Engineering. 166:82-88
To deal with the strong attenuation of neutral particle flux in matter, like in radiation shielding studies, several techniques are used in Monte Carlo transport codes (MCNP, MCBEND, TRIPOLI, etc.) to accelerate the simulation of neutron or gamma ray
Publikováno v:
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo.
In the context of reactor physics, one is often called to relate the physical properties of a medium to the statistics of the random trajectories of the neutrons flowing through it. For instance, Cauchy’s formula establishes a link between the aver
Publikováno v:
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo.
In this paper, we discuss some improvements we recently implemented in the Monte-Carlo code TRIPOLI-4® associated with the homogenization and collapsing of subassemblies cross sections. The improvement offered us another approach to get critical mul
Autor:
A. Tsilanizara, T. D. Huynh, N. Gilardi, J. M. Martinez, C. Jouanne, S. Lahaye, Cheikh M. Diop
Publikováno v:
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo.
The knowledge of the decay heat quantity and the associated uncertainties are important issues for the safety of nuclear facilities. Many codes are available to estimate the decay heat. ORIGEN, FISPACT, DARWIN/PEPIN2 are part of them. MENDEL is a new