836 articles – 5610 Notices  [english version]
.:. Consultation > Par auteur du laboratoire > Allibert .:.
26 documents classés par :

Preliminary design studies of the draining thanks for the molten salt fast reactor
Merle-Lucotte E., Allibert M., Heuer D., Brovchenko M., Laureau A. et al
Dans ENC 2014 Conference Proceedings - European Nuclear Conference (ENC 2014), France (2014) [in2p3-00990875 - version 1]
Production and release of ISOL beams from molten fluoride salt targets
Mendonca T.M., Hodak R., Ghetta V., Allibert M., Heuer D. et al
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 329 (2014) 1-5 [in2p3-00968478 - version 1]
The molten salt reactor (MSR) in generation IV: Overview and perspectives
Serp J., Allibert M., Beneš O., Delpech S., Feynberg O. et al
Progress in Nuclear Energy In press, corrected proof (2014) [in2p3-00957762 - version 1]
Towards the thorium fuel cycle with molten salt fast reactors
Heuer D., Merle-Lucotte E., Allibert M., Brovchenko M., Ghetta V. et al
Annals of Nuclear Energy 64 (2013) 421-429 [in2p3-00908813 - version 1]
Coupled study of the Molten Salt Fast Reactor core physics and its associated reprocessing unit
Doligez X., Heuer D., Merle-Lucotte E., Allibert M., Ghetta V.
Annals of Nuclear Energy 64 (2013) 430-440 [in2p3-00908811 - version 1]
Recommandations for a demonstrator of Molten Salt Fast Reactor
Merle-Lucotte E., Heuer D., Allibert M., Brovchenko M., Ghetta V. et al
In Proceedings of the International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) - International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13), France (2013) [in2p3-00797723 - version 1]
Design-Related Studies for the Preliminary Safety Assessment of the Molten Salt Fast Reactor
Brovchenko M., Heuer D., Merle-Lucotte E., Allibert M., Ghetta V. et al
In Nuclear Science and Engineering - Physics in Reactors Topical Meeting (PHYSOR 2012), United States (2012) [in2p3-00688210 - version 1]
Preliminary design assessment of the molten salt fast reactor
Merle-Lucotte E., Heuer D., Allibert M., Brovchenko M., Ghetta V. et al
In ENC 2012 Transactions - European Nuclear Conference (ENC 2012), United Kingdom (2012) [in2p3-00766659 - version 1]
Launching the thorium fuel cycle with the Molten Salt Fast Reactor
Merle-Lucotte E., Heuer D., Allibert M., Brovchenko M., Capellan N. et al
In Proceedings of ICAPP 2011 - 2011 International Congress on Advances in Nuclear Power Plants (ICAPP 2011), France (2011) [in2p3-00590301 - version 1]
Simulation tools and new developments of the molten salt fast reactor
Heuer D., Merle-Lucotte E., Allibert M., Doligez X., Ghetta V.
RGN Revue Générale Nucléaire 6 (2010) 95-100 [in2p3-00561186 - version 1]
Simulation tools and new developments of the Molten Salt Fast Reactor
Merle-Lucotte E., Doligez X., Heuer D., Allibert M., Ghetta V.
In ENC 2010 Transactions - European Nuclear Conference (ENC 2010), Spain (2010) [in2p3-00488448 - version 1]
Yttria-stabilized zirconia as membrane material for electrolytic deoxidation of CaO-CaCl2 melts
Martin A., Poignet J.C., Fouletier J., Allibert M., Lambertin D. et al
Journal of Applied Electrochemistry 40 (2010) 533-542 [in2p3-00462297 - version 1]
Extraction liquide-liquide
Allibert M., Ghetta V.
In Sels fondus à haute température - Ecole Sels Fondus à Haute Température, France (2008) [in2p3-00441650 - version 1]
Thermodynamique chimique
Allibert M.
In Sels fondus à haute température - Ecole Sels Fondus à Haute Température, France (2008) [in2p3-00441647 - version 1]
Numerical tools for molten salt reactors simulation
Doligez X., Heuer D., Merle-Lucotte E., Ghetta V., Allibert M.
In Proceedings of Global 2009 - International Conference GLOBAL 2009 "The Nuclear Fuel Cycle: Sustainable Options & Industrial Perspectives", France (2009) [in2p3-00422496 - version 1]
Optimizing the burning efficiency and the deployment capacities of the molten salt fast reactor
Merle-Lucotte E., Heuer D., Allibert M., Doligez X., Ghetta V.
In Proceedings of Global 2009 - International Conference GLOBAL 2009 "The Nuclear Fuel Cycle: Sustainable Options & Industrial Perspectives", France (2009) [in2p3-00422484 - version 1]
fulltext access Minimizing the fissile inventory of the molten salt fast reactor
Merle-Lucotte E., Heuer D., Allibert M., Doligez X., Ghetta V.
In Proc. of Advances in Nuclear Fuel Management IV (ANFM IV) CD Rom - Advances in Nuclear Fuel Management IV (ANFM IV), United States (2009) [in2p3-00385378 - version 1]
Reactor physic and reprocessing scheme for innovative molten salt reactor system
Delpech S., Merle-Lucotte E., Heuer D., Allibert M., Ghetta V. et al
Journal of Fluorine Chemistry 130 (2009) 11-17 [in2p3-00355091 - version 1]
fulltext access Optimization and simplification of the concept of non-moderated Thorium Molten Salt Reactor
Merle-Lucotte E., Heuer D., Allibert M., Doligez X., Ghetta V. et al
Dans Proceedings of International Conference on the Physics of Reactors "Nuclear Power: A Sustainable Resource" - International Conference on the Physics of Reactors - PHYSOR 2008, Suisse (2008) [in2p3-00326466 - version 1]
Thorium Molten Salt Reactor reprocessing unit: characterization and influence on the core behaviour.
Doligez X., Heuer D., Merle-Lucotte E., Ghetta V., Allibert M. et al
In Proc. of the 2008 Joint Symposium on Molten Salts - 2008 Joint Symposium on Molten Salts, Japan (2008) [in2p3-00336542 - version 1]
Introduction to the physics of molten salt reactors
Merle-Lucotte E., Heuer D., Allibert M., Ghetta V., Le Brun C.
In Materials Issues for Generation IV Systems. Status, open questions and challenges - NATO Advanced Study Institute on Materials for Generation IV Nuclear Reactors (MATGEN-IV), France (2007) [in2p3-00187115 - version 1]
fulltext access The thorium molten salt reactor: Launching the thorium cycle while closing the current fuel cycle
Merle-Lucotte E., Heuer D., Allibert M., Ghetta V., Le Brun C. et al
In Proceedings of the ENC 2007 (CD-Rom) - European Nuclear Conference (ENC 2007), Belgium [in2p3-00186944 - version 1]
The non-moderated TMSR: an efficient actinide burner and a very promising thorium breeder
Merle-Lucotte E., Heuer D., Le Brun C., Allibert M., Ghetta V. et al
In Proceedings of the GLOBAL 07 (CD-Rom) - Global 07 - Advanced Nuclear Fuel Cycles and Systems, United States [in2p3-00187107 - version 1]
fulltext access Etude par simulation numérique du retraitement des déchets du T.M.S.R. (Thorium Molten Salt Reactor)
Doligez X., Allibert M., Ghetta V., Heuer D., Merle-Lucotte E.
Rapport de recherche (2007) 34 p. [in2p3-00180193 - version 1]
fulltext access The TMSR as Actinide Burner and Thorium Breeder
Merle-Lucotte E., Heuer D., Le Brun C., Allibert M., Ghetta V.
Rapport de recherche (2007) 5 p. [in2p3-00143680 - version 1]
fulltext access Optimized transition from the reactors of second and third generations to the Thorium Molten Salt Reactor
Merle-Lucotte E., Heuer D., Allibert M., Ghetta V., Le Brun C. et al
Dans Proceedings of the ICAPP 2007 - ICAPP 2007 : International Congress on Advances in Nuclear Power Plants, France [in2p3-00135149 - version 1]