Zobrazeno 1 - 10
of 15
pro vyhledávání: '"Alexis Jinaphanh"'
Publikováno v:
Journal of Nuclear Engineering, Vol 2, Iss 2, Pp 132-151 (2021)
Modal expansions based on k-eigenvalues and α-eigenvalues are commonly used in order to investigate the reactor behaviour, each with a distinct point of view: the former is related to fission generations, whereas the latter is related to time. Well-
Externí odkaz:
https://doaj.org/article/cac80cd3984043c6b13c99ad9f77a2a4
Autor:
Tran Kim Tuyet, Alexis Jinaphanh, Cédric Jouanne, Frédéric Gérardin, Sébastien Lemaire, Andrea Zoia
Publikováno v:
Nuclear Science and Engineering. :1-17
Publikováno v:
Journal of Nuclear Engineering, Vol 2, Iss 14, Pp 132-151 (2021)
Journal of Nuclear Engineering
Volume 2
Issue 2
Pages 14-151
Journal of Nuclear Engineering
Volume 2
Issue 2
Pages 14-151
Modal expansions based on k-eigenvalues and α-eigenvalues are commonly used in order to investigate the reactor behaviour, each with a distinct point of view: the former is related to fission generations, whereas the latter is related to time. Well-
Publikováno v:
Annals of Nuclear Energy. 134:244-249
The Institut de Radioprotection et de Surete Nucleaire (IRSN) is the French public service expert in nuclear and radiation risks with activities that cover all the related scientific and technical issues. IRSN provides expertise in support of radiati
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2020, 137, pp.107033-. ⟨10.1016/j.anucene.2019.107033⟩
Annals of Nuclear Energy, 2020, 137, pp.107033. ⟨10.1016/j.anucene.2019.107033⟩
Annals of Nuclear Energy, Elsevier Masson, 2020, 137, pp.107033-. ⟨10.1016/j.anucene.2019.107033⟩
Annals of Nuclear Energy, 2020, 137, pp.107033. ⟨10.1016/j.anucene.2019.107033⟩
International audience; Time or $\alpha$ eigenvalues are key to several applications in reactor physics, encompassing start-up analysis and reactivity measurements. In a series of recent works, a Monte Carlo method has been proposed in order to estim
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::44c13f7310c1b249650f1d8f0bb5daf8
https://hal.archives-ouvertes.fr/hal-03488748
https://hal.archives-ouvertes.fr/hal-03488748
Autor:
Nicolas Leclaire, Alexis Jinaphanh
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2018, 114, pp.395-406. ⟨10.1016/j.anucene.2017.12.051⟩
Annals of Nuclear Energy, Elsevier Masson, 2018, 114, pp.395-406. ⟨10.1016/j.anucene.2017.12.051⟩
International audience; The MORET code is a simulation tool that solves the transport equation for neutrons using the Monte Carlo method. A perturbation procedure using first order Taylor expansion series in the continuous-energy calculation for isot
Publikováno v:
Annals of Nuclear Energy. 164:108563
Matrix-filling Monte Carlo methods can be successfully used to estimate higher-order k- and α -eigenmodes and eigenvalues of the Boltzmann equation. A novel matrix-filling Monte Carlo approach has been recently developed in T ripoli -4® in order to
Publikováno v:
Annals of Nuclear Energy. 162:108486
The time–eigenvalues α of the natural mode equation are calculated for the CROCUS benchmark models corresponding to 11 water levels using suitable modifications of the power iteration of fission source in the MCNP-5 and TRIPOLI-4® codes. To model
Autor:
Andrea Zoia, Alexis Jinaphanh
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2019, 133, pp.678-687. ⟨10.1016/j.anucene.2019.06.062⟩
Annals of Nuclear Energy, 2019, 133, pp.678-687. ⟨10.1016/j.anucene.2019.06.062⟩
Annals of Nuclear Energy, Elsevier Masson, 2019, 133, pp.678-687. ⟨10.1016/j.anucene.2019.06.062⟩
Annals of Nuclear Energy, 2019, 133, pp.678-687. ⟨10.1016/j.anucene.2019.06.062⟩
TRIPOLI-4® is a registered trademark of CEA; International audience; Time eigenvalues emerge in several key applications related to neutron transport problems, including reactor start-up and reactivity measurements. In this context,experimental vali
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::fee1b8fcc155aa45b1f7099db15b1cb9
https://hal.archives-ouvertes.fr/hal-03487336
https://hal.archives-ouvertes.fr/hal-03487336
Publikováno v:
Nuclear Science and Engineering
Nuclear Science and Engineering, 2016, 184 (1), pp.53-68. ⟨10.13182/NSE16-2⟩
Nuclear Science and Engineering, 2016, 184 (1), pp.53-68. ⟨10.13182/NSE16-2⟩
International audience; A continuous-energy sensitivity coefficient calculation to nuclear data capability has been recently developed in Version 5.C.1 of the MORET Monte Carlo code developed at Institut de Radioprotection et de Sûreté nucléaire (