811 articles – 5031 Notices  [english version]
.:. Consultation > Par auteurs du labo > Allibert .:.
21 documents classés par :
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Recommandations for a demonstrator of Molten Salt Fast Reactor
Merle-Lucotte E., Heuer D., Allibert M., Brovchenko M., Ghetta V. et al
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13), France (2013) [in2p3-00797723 - version 1]
Preliminary design assessment of the molten salt fast reactor
Merle-Lucotte E., Allibert M., Brovchenko M., Ghetta V., Heuer D. et al
European Nuclear Conference (ENC 2012), Royaume-Uni (2012) [in2p3-00766659 - version 1]
Preliminary safety calculations to improve the design of Molten Salt Fast Reactor
Brovchenko M., Heuer D., Merle-Lucotte E., Allibert M., Capellan N. et al
In PHYSOR 2012 Advances in Reactor Physics - Physics in Reactors Topical Meeting (PHYSOR 2012), United States (2012) [in2p3-00688210 - 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]
Neutronic and radioactivity assessment for the non-moderated thorium molten salt reactor (TMSR-NM) reprocessing unit
Doligez X., Heuer D., Merle-Lucotte E., Allibert M., Delpech S. et al
2008 Joint Symposium on Molten Salts, Japon (2008) [in2p3-00336542 - 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
In Proceedings of International Conference on the Physics of Reactors "Nuclear Power: A Sustainable Resource" - International Conference on the Physics of Reactors - PHYSOR 2008, Switzerland (2008) [in2p3-00326466 - 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
Dans Proceedings of the ENC 2007 (CD-Rom) - European Nuclear Conference (ENC 2007), Belgique [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
Dans Proceedings of the GLOBAL 07 (CD-Rom) - Global 07 - Advanced Nuclear Fuel Cycles and Systems, États-Unis [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.
Research report (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.
Research report (2007) 5 p. [in2p3-00143680 - version 1]