Zobrazeno 1 - 7
of 7
pro vyhledávání: '"Jean Marc Palau"'
APOLLO3 homogenization techniques for transport core calculations—application to the ASTRID CFV core
Autor:
Jean-François Vidal, Pascal Archier, Bastien Faure, Valentin Jouault, Jean-Marc Palau, Vincent Pascal, Gérald Rimpault, Fabien Auffret, Laurent Graziano, Emiliano Masiello, Simone Santandrea
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 7, Pp 1379-1387 (2017)
This paper presents a comparison of homogenization techniques implemented in the APOLLO3 platform for transport core calculations: standard scalar flux weighting and new flux–moment homogenization, in different combinations with (or without) leakag
Externí odkaz:
https://doaj.org/article/477c8ca3a3094f79947d6b834be5c8d7
Autor:
Fiona Desplats, Pascal Archier, Jean-François Vidal, Jean-Marc Palau, Roland Lenain, Emiliano Masiello
Publikováno v:
Annals of Nuclear Energy. 170:108970
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d4c826913b8cd029db863933ad4229f3
https://doi.org/10.1016/j.anucene.2022.108970
https://doi.org/10.1016/j.anucene.2022.108970
Publikováno v:
Annals of Nuclear Energy. 170:108993
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bc2636cfe24aebbafbeae6ad132e7fec
https://doi.org/10.1016/j.anucene.2022.108993
https://doi.org/10.1016/j.anucene.2022.108993
Autor:
Jean Michel Ruggieri, Benedicte Roque, Christos Trakas, Didier Biron, Jean Marc Palau, Alain Santamarina, Philippe Bioux, Herve Toubon, François Storrer, Guy Willermoz, Dominique Hittner
Publikováno v:
Journal of Nuclear Science and Technology. 39:1357-1360
The aim of this paper is to review the activity of the French Committee on Nuclear Data (CFDN) regarding priority of data needs for R&D programs and industrial applications in France under investigation at FRAMATOME, EDF, COGEMA, and CEA. The target
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::70a85dbc6e3fe31a3c3064be515abd5a
https://doi.org/10.1080/00223131.2002.10875356
https://doi.org/10.1080/00223131.2002.10875356
Autor:
David Bernard, Jean-Marc Palau
Publikováno v:
Journal of Nuclear Science and Technology. 39:912-915
This paper presents a 3D uncertainty propagation methodology and its application to the case of a small heterogeneous reactor system (“slab” reactor benchmark). Key neutron parameters (keff, reacti...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8f2959d4fee5dec8c87b0f87074ef834
https://doi.org/10.1080/00223131.2002.10875247
https://doi.org/10.1080/00223131.2002.10875247
Autor:
Desplats, Fiona
Publikováno v:
Chemical and Process Engineering. Université Grenoble Alpes [2020-..], 2022. English. ⟨NNT : 2022GRALI062⟩
Neutronic calculations are traditionally performed using either deterministic or stochastic methods. Deterministic codes discretize the phase space using models to solve the transport equations which can induce biases. Stochastic codes use random sam
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=od______3515::137948e37b8a568b1684b65fb2f9050b
https://theses.hal.science/tel-03997855/document
https://theses.hal.science/tel-03997855/document
Autor:
Zajaczkowski, Maciej
Publikováno v:
Accelerator Physics [physics.acc-ph]. Université Grenoble Alpes [2020-..], 2020. English. ⟨NNT : 2020GRALI054⟩
In order to improve passive safety of Sodium-cooled Fast Reactors (SFR) in case of unprotected transients such as Unprotected Loss of Flow (ULOF) or Unprotected Transient Overpower (UTOP), The French Alternative Energies and Atomic Energy Commission
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::94232ce4235e38ba09152ea4886502e4
https://theses.hal.science/tel-03116415
https://theses.hal.science/tel-03116415