Zobrazeno 1 - 8
of 8
pro vyhledávání: '"Frédéric Damian"'
Autor:
A. Stefanova, Pavlin Groudev, Pietro Mosca, Frédéric Damian, Clément Lafaurie, Barbara Calgaro, Alberto Previti, Sandro Paci, Victor Sanchez-Espinoza, Neli Zaharieva, D. Verrier, Nicola Forgione, Olivier Bernard, Nicolas Dos Santos, Luigi Mercatali, B. Vezzoni, Daniele Tomatis, Ulrich Bieder, Artur Hashymov, Adrien Willien
Publikováno v:
Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics.
CAMIVVER (Codes And Methods Improvements for VVER comprehensive safety assessment) is a three years project launched under the European Union research program HORIZON 2020. The main aim of the Project is to develop and improve computer codes and meth
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8c17425ffa7940ba3bb60deb66dd0b66
https://doi.org/10.1115/icone28-64169
https://doi.org/10.1115/icone28-64169
Autor:
Denis Janin, Frédéric Damian
Publikováno v:
Revue Générale Nucléaire. :56-59
Les petits réacteurs modulaires (SMR) à eau pressurisée actuellement en développement sont plus gourmands en combustible que les réacteurs à eau pressurisée d’aujourd’hui. Plusieurs pistes existent pour limiter la consommation d’uranium
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b58e466562a5b978106ac70e2a1dd323
https://doi.org/10.1051/rgn/20185056
https://doi.org/10.1051/rgn/20185056
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4016bcf4e0280222dc6704bc2e8e89d1
https://doi.org/10.1016/j.anucene.2014.07.053
https://doi.org/10.1016/j.anucene.2014.07.053
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2015, 75, pp.627-634. ⟨10.1016/j.anucene.2014.09.014⟩
Annals of Nuclear Energy, 2015, 75, pp.627-634. ⟨10.1016/j.anucene.2014.09.014⟩
Annals of Nuclear Energy, Elsevier Masson, 2015, 75, pp.627-634. ⟨10.1016/j.anucene.2014.09.014⟩
Annals of Nuclear Energy, 2015, 75, pp.627-634. ⟨10.1016/j.anucene.2014.09.014⟩
International audience; Several technological issues, such as reactor start-up analysis or kinetics studies of accelerator-driven systems, demand the asymptotic time behaviour of neutron transport to be assessed. Typically, this amounts to solving an
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::eeb9f8abe3ff0824b4e80e0b1ba272d8
https://doi.org/10.1016/j.anucene.2014.09.014
https://doi.org/10.1016/j.anucene.2014.09.014
Autor:
Antonella Li Puma, Clement Fausser, Pierre-Yves Cayla, Yi-Kang Lee, Jean-Charles Jaboulay, Jean-Christophe Trama, Frédéric Damian
Publikováno v:
Fusion Engineering and Design. 89:2174-2178
3D Monte Carlo transport codes are extensively used in neutronic analysis, especially in radiation protection and shielding analyses for fission and fusion reactors. TRIPOLI-4® is a Monte Carlo code developed by CEA. The aim of this paper is to show
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::72daab464be93e76be60a7e20b8cc996
https://doi.org/10.1016/j.fusengdes.2014.02.038
https://doi.org/10.1016/j.fusengdes.2014.02.038
Autor:
Hiroshi Sagara, Frédéric Damian, Chi Young Han, Erina Hamase, Masaki Saito, Christine Poinot-salanon
Publikováno v:
Ann. Nucl. Energy. 54:76-84
The present paper is focused on the feasibility of reduced-moderation water reactor (RMWR) which could simultaneously achieve the extension of core life-time, and highly protected plutonium (Pu) breeding performance with short compound system doublin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5840432fb63f9e1678db14ddd46bf82f
http://t2r2.star.titech.ac.jp/cgi-bin/publicationinfo.cgi?q_publication_content_number=CTT100751853
http://t2r2.star.titech.ac.jp/cgi-bin/publicationinfo.cgi?q_publication_content_number=CTT100751853
Autor:
Alain Santamarina, Guillaume Truchet, Pierre Leconte, Frédéric Damian, Emeric Brun, Andrea Zoia
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, 2015, 85, pp.17-26. ⟨10.1016/j.anucene.2015.04.025⟩
Annals of Nuclear Energy, 2015, 85, pp.17-26. ⟨10.1016/j.anucene.2015.04.025⟩
International audience; The analysis of neutron kinetics relies on the knowledge of adjoint-weighted kinetics parameters, which are key to safety issues in the context of transient or accidental reactor behavior. The Iterated Fission Probability (IFP
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d7be54242c9cda1aae34ba007b4b1566
https://cea.hal.science/cea-02387020/document
https://cea.hal.science/cea-02387020/document
Publikováno v:
Nuclear Technology. 145:266-274
High-temperature gas-cooled reactors (HTRs) are able to accommodate a wide variety of mixtures of fissile and fertile materials without any significant modification of the core design. This flexibi...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::761f284d6046c2f429c069931638c9a4
https://doi.org/10.13182/nt04-a3476
https://doi.org/10.13182/nt04-a3476