Zobrazeno 1 - 10
of 136
pro vyhledávání: '"B Cochet"'
Autor:
B. Cochet, Nicolas Leclaire
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2021, 155, pp.1-12. ⟨10.1016/j.anucene.2021.108164⟩
Annals of Nuclear Energy, Elsevier Masson, 2021, 155, pp.1-12. ⟨10.1016/j.anucene.2021.108164⟩
The present paper focuses on the modeling of the CROCUS reactor with the French MORET 5 continuous energy code and compares keff, anti-reactivity effects (variation of keff normalized to keff due to the insertion of an absorber), sensitivity coeffici
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3e3845a2f134848c660f96a91e7b8791
https://hal.archives-ouvertes.fr/hal-03202427
https://hal.archives-ouvertes.fr/hal-03202427
Akademický článek
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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 (
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::07310e74c206936fa196a893d1dba226
https://doi.org/10.13182/nse16-2
https://doi.org/10.13182/nse16-2
Conference
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Publikováno v:
EPJ Web of Conferences, Vol 146, p 06009 (2017)
For many years now, IRSN has developed its own Monte Carlo continuous energy capability, which allows testing various nuclear data libraries. In that prospect, a validation database of 1136 experiments was built from cases used for the validation of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5786109f2df6d599fce4b361432a56ed
https://doaj.org/article/021f96216e2248f8ad36647bc40b2ba6
https://doaj.org/article/021f96216e2248f8ad36647bc40b2ba6
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2015, 82, pp.74-84. ⟨10.1016/j.anucene.2014.08.022⟩
Annals of Nuclear Energy, Elsevier Masson, 2015, 82, pp.74-84. ⟨10.1016/j.anucene.2014.08.022⟩
International audience; The MORET code is a simulation tool that solves the transport equation for neutrons using the Monte Carlo method. It allows users to model complex three-dimensional geometrical configurations, describe the materials, define th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::85c1f1822cfeef09febdb726c82047a7
https://hal.archives-ouvertes.fr/hal-02570474
https://hal.archives-ouvertes.fr/hal-02570474
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2015, 76, pp.530-539. ⟨10.1016/j.anucene.2014.10.033⟩
Annals of Nuclear Energy, Elsevier Masson, 2015, 76, pp.530-539. ⟨10.1016/j.anucene.2014.10.033⟩
International audience; The present paper aims at providing experimental validation for the use of the MORET 5 code for advanced concepts of reactor involving thorium and heavy water. It therefore constitutes an opportunity to test and improve the th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ee24b010358672041c758878beba4b97
https://hal.archives-ouvertes.fr/hal-02567321
https://hal.archives-ouvertes.fr/hal-02567321
Publikováno v:
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo.
The MORET 5 Monte Carlo code includes two calculation routes: a multi-group route based on cross-sections calculated from various preliminary cell codes and a continuous energy calculation route. The criticality experimental validation database is ma
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2235b85514621568d1de4115f7fe3ceb
https://doi.org/10.1051/snamc/201405311
https://doi.org/10.1051/snamc/201405311
Publikováno v:
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo.
As technical support of the French Nuclear Safety Authority, IRSN has been developing the MORET Monte Carlo code for many years in the framework of criticality safety assessment and is now working to extend its application to reactor physics. For tha
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8c4ad4c5fcd06587fcd5394f47362a00
https://doi.org/10.1051/snamc/201401101
https://doi.org/10.1051/snamc/201401101
Publikováno v:
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo.
Depletion codes such as VESTA are used to calculate the evolution of a material subjected to radiation (be it neutrons or another type of particle) for a wide variety of applications in the fields of nuclear safety, radiation protection and environme
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6e2e0f6cca87774fa7bbfbe0f88d7039
https://doi.org/10.1051/snamc/201403603
https://doi.org/10.1051/snamc/201403603