MSFR - Bibliography

Articles

Book chapters and reports

Proceedings

PhD and HDR thesis

Internships (description / reports)

Generation IV International Forum: publications and documents on MSR

Further information

Articles

• A. Laureau, A. Bellè, M. Allibert, D. Heuer, E. Merle, A. Pautz, “Unmoderated molten salt reactors design optimisation for power stability”, Annals of Nuclear Energy, 177, p. 109265 (2022) - PDF version
• M. Allibert, E. Merle, S. Delpech, D. Gerardin, D. Heuer, A. Laureau, S. Moreau, “Preliminary Proliferation Study of the Molten Salt Fast Reactor”, EPJ Nuclear Sci. Technol. 6, 5 (2020), https//doi.org/10.1051/epjn/2019062 - PDF version (open access)
• D. Gerardin, A.C. Uggenti, S. Beils, A. Carpignano, S. Dulla, E. Merle, D. Heuer, A. Laureau, M. Allibert, “Identification of the Postulated Initiating Events with MLD and FFMEA for the Molten Salt Fast Reactor”, Nuclear Engineering and Technology (2019), doi: 10.1016/j.net.2019.01.009 - PDF version (open access)
• M. Brovchenko et al. (M. Brovchenko, D. Heuer, A. Laureau, E. Merle), "Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects", EPJ Nuclear Sci. Technol. 5 (2019), doi: https://doi.org/10.1051/epjn/2018052  - PDF version (open access)
• S. Wang, M. Massone, A. Rineiski, E. Merle-Lucotte, A. Laureau, D. Gérardin, D. Heuer, M. Allibert, "A passive decay heat removal system for emergency draining tanks of molten salt reactors", Nucl. Eng. and Design 341, 423-431 (2019)
• A. Laureau, D. Heuer, E. Merle-Lucotte, P. Rubiolo, M. Allibert, M. Aufiero, “Transient coupled calculations of the Molten Salt Fast Reactor using the Transient Fission Matrix approach”, Nuclear Engineering and Design, volume 316, p. 112–124 (2017) - PDF version
• A. Laureau, M. Aufiero, P. Rubiolo, E. Merle-Lucotte, D. Heuer, “Transient Fission Matrix: kinetic calculation and kinetic parameters β_eff and Λ_eff calculation”, Annals of Nuclear Energy, volume 85, p. 1035–1044 (2015) - PDF version - ScienceDirect Version
• R. Li, S. Wang, 1A. Rineiski, D. Zhang, E. Merle-Lucotte, “Transient Analyses for a Molten Salt Fast Reactor with Optimized Core Geometry”, Nuclear Engineering and Design (2015) - PDF version (soon)
• D. Heuer, E. Merle-Lucotte, M. Allibert, M. Brovchenko, V. Ghetta, P. Rubiolo , “Towards the Thorium Fuel Cycle with Molten Salt Fast Reactors”,  Annals of Nuclear Energy 64, 421–429 (2014) - PDF version
• M. Aufiero, M. Brovchenko, A. Cammi, I. Clifford, O. Geoffroy, D. Heuer, A. Laureau, M. Losa, L. Luzzi,, E. Merle-Lucotte, M.E. Ricotti, H. Rouch, “Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: analytical, deterministic and Monte Carlo approaches”, Annals of Nuclear Energy 65, 78–90 (2014) - Article in ResearchGate
• J. Serp, M. Allibert, O. Beneš, S. Delpech, O. Feynberg, V. Ghetta, D. Heuer, D. Holcomb, V. Ignatiev, J.L. Kloosterman, L. Luzzi, E. Merle-Lucotte, J. Uhlíř, R. Yoshioka, D. Zhimin, “The molten salt reactor (MSR) in generation IV: Overview and Perspectives”, Prog. Nucl. Energy, 1-12 (2014) - PDF version
• H. Rouch, O. Geoffroy, P. Rubiolo, A. Laureau, D. Heuer,M. Brovchenko, E. Merle-Lucotte, “Preliminary Thermalhydraulic Core Design of a Molten Salt Fast Reactor”, Annals of Nuclear Energy, Vol. 64, p 449–456 (2014) - PDF version
• X. Doligez, D. Heuer, E. Merle Lucotte, M. Allibert, V. Ghetta, “Coupled study of the Molten Salt Fast Reactor core physics and its associated reprocessing unit”, Annals of Nuclear Energy 64, 430–440 (2014)
• M. Brovchenko, D. Heuer, E. Merle-Lucotte, M. Allibert, V. Ghetta, A. Laureau, P. Rubiolo, “Design-related Studies for the Preliminary Safety Assessment of the Molten Salt Fast Reactor”, Nuclear Science and Engineering,175, 329–339 (2013) - PDF Version
• S. Delpech, E. Merle-Lucotte, D. Heuer, M. Allibert, V. Ghetta, C. Le-Brun, L. Mathieu, G. Picard, “Reactor physics and reprocessing scheme for innovative molten salt reactor system”, J. of Fluorine Chemistry, 130 Issue 1, p. 11-17 (2009) - PDF Version
• D. Heuer et E. Merle-Lucotte,“Un concept innovant : les réacteurs à sels fondus”, Science au Présent 2009, complément annuel scientifique de l'Encyclopedia Universalis (2009) - PDF Version
• L. Mathieu, D. Heuer, E. Merle-Lucotte, R. Brissot, C. Le Brun, D. Lecarpentier, E. Liatard, J.M. Loiseaux, O. Méplan, A. Nuttin,“Possible Configurations for the TMSR and advantages of the Fast Non Moderated Version”, Nuclear Science and Engineering 161, p. 78–89 (2009) - PDF Version
• E. Merle-Lucotte, L. Mathieu, D. Heuer et al,“Influence of the reprocessing and salt composition on molten salt reactor behavior”, Nuclear Technology, Volume 163 Number 3, pp 358-365 (2008) - PDF Version
• E. Merle-Lucotte, D. Heuer, M. Allibert, V. Ghetta, C. Le Brun,“Introduction to the Physics of Molten Salt Reactor”, Materials Issues for Generation IV Systems, NATO Science for Peace and Security Series - B, Editions Springer, pages 501-521 (2008) - PDF Version
• C.W. Forsberg, C. Renault, C. Le Brun, E. Merle-Lucotte, V. Ignatiev,“Liquid Salt Applications and Molten Salt Reactors”, Revue Générale du Nucléaire N° 4/2007, p 63-71 (2007) - PDF Version
• E. Merle-Lucotte, D. Heuer, C. Le Brun, J.-M. Loiseaux,“Scenarios for a Worldwide Deployment of Nuclear Power”, International Journal of Nuclear Governance, Economy and Ecology, Volume 1, Issue 2, pp 168-192 (2006) - PDF Version
• L. Mathieu, D. Heuer, R. Brissot, C. Le Brun, E. Liatard, J.M. Loiseaux, O. Méplan, E. Merle-Lucotte, A. Nuttin, J. Wilson, C. Garzenne, D. Lecarpentier, E. Walle,“The Thorium Molten Salt Reactor: Moving on from the MSBR”, Prog. in Nucl. En., vol 48, pp. 664-679 (2006) - PDF Version
• D. Heuer, E. Merle-Lucotte, L. Mathieu,“Concept de réacteurs à sels fondus en cycle thorium sans modérateur”, Revue Générale du Nucléaire N° 5/2006, p 92-99 (2006) - PDF Version
• A. Nuttin D. Heuer, A.Billebaud, R. Brissot, C. Garzenne, C. Le Brun, D. Lecarpentier, E. Liatard, J.M. Loiseaux, O. Méplan, E. Merle-Lucotte, J. Wilson,“Potential of Thorium Molten Salt Reactors”, Prog. in Nucl. En., vol 46, p. 77-99 (2005) - PDF Version

  Book chapters and reports

• "IAEA Technical Reports Series on the Status of Molten Salt Reactor Technology", Technical Report Series (TRS no.489), International Atomic Energy Agency, Vienna, Austria (2021) – preprint IAEA
• M. Allibert, S. Beils, S. Bourg, M. Brovchenko, G. Campioni, B. Carluec, P. Chamelot, M. Delpech, S. Delpech, P. Gauthé, D. Gerardin, A. Gerschenfeld, Y. Gorsse, J. Guidez, D. Heuer, E. Ivanov, A. Laureau, D. Lecarpentier, J. Martinet, E. Merle, J. Serpe, "Rapport Scientifique des Journées MSR des 22-23 mars 2018", Massy (2018) - http://irfu.cea.fr/Meetings/seminaires-MSR/MSR_Rapport_final.pdf
• Chapter Worlwide Activities, "Molten Salt Reactors and Thorium Energy", Dolan T. J. (ed.), Woodhead Publishing (2017)
• E. Merle-Lucotte, M. Allibert, M. Brovchenko, D. Heuer, V. Ghetta, A. Laureau, P.Rubiolo, Chapter “Introduction to the Physics of Thorium Molten Salt Fast Reactor (MSFR) Concepts”, Thorium Energy for the World, Springer International Publishing, Switzerland (2016) - PDF version
• M. Allibert et al.,“Introduction of Thorium in the Nuclear Fuel Cycle. Short-to long-term considerations”, Report No. NEA--7224. Organisation for Economic Co-Operation and Development (2015) - PDF version
• Michel Allibert, Manuele Aufiero, Mariya Brovchenko, Sylvie Delpech, Véronique Ghetta, Daniel Heuer, A. Laureau, Elsa Merle-Lucotte, “Chapter 7 - Molten Salt Fast Reactors”, Handbook of Generation IV Nuclear Reactors, Woodhead Publishing Series in Energy (2015) - PDF version

Proceedings

• A. Laureau, E. Merle, “Tool developments based on OpenMC toward neutron kinetics and uncertainty propagation with the TFM approach using OpenFOAM mesh and Correlated Sampling”, Proceedings of Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C2023), Niagara Falls, Canada (2023) - PDF version
• T. Sornay,  T. Boisseau, A. Laureau, A. Lemarchand , E. Merle, F. Vaiana, “ Coupled Neutronics and Thermal-Hydraulics Calculations on the Molten Salt Fast Reactor: Identification and Study of Cliff Edge Effects”, Proceedings of Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C2023), Niagara Falls, Canada (2023) - PDF version

• H. Pitois, D. Heuer, A. Laureau, E. Merle, M. Allibert, S. Delpech, “A closed fuel cycle option using the MSFR concept with chloride salts and the U/Pu cycle”, Proceedings of the Global2022 International Conference, Reims, France (2022) - PDF version
• L. Tillard, L. Mesthiviers, E. Capelli, D. Heuer, R. Maréchaux, Y. Meridiano, E. Merle, B. Morel, I. Morlaes, G. Senentz, “Estimation of the vitrified canister production for PWR fleets integrating MSRs with different fuel cycle strategies”, Proceedings of the Global2022 International Conference, Reims, France (2022) - PDF version
• E. Merle, B. Carluec, M. Allibert, F. Bertrand, T. Boisseau, E. Courtin, D. Heuer, A. Laureau, “Considerations on the new safety paradigm provided by liquid-fuelled reactors - Illustration on the MSFR concept”, Proceedings of the IAEA Technical Meeting on the Safety of High Temperature Gas Cooled Reactors and Molten Salt Reactors, IAEA, Vienne, Autriche (2022) - PDF version
• L. Mesthiviers, D. Heuer, E. Merle, G. Grassi, B. Morel, G. Senentz, "Study on actinide conversion capabilities of Molten Salt Reactors (MSR)”, Proceedings of the International Conference on Fast Reactors and Related Fuel Cycles FR22: Sustainable Clean Energy for the Future, IAEA, Vienne, Autriche (2022) - PDF version
• T. Le Meute, F. Bertrand, N. Seiler, E. Merle, D. Heuer, “Modelling of postulated reactivity insertion in a Generation IV Molten Salt Reactor" , Proceedings of the International Conference on Fast Reactors and Related Fuel Cycles FR22: Sustainable Clean Energy for the Future, IAEA, Vienne, Autriche (2022) - PDF version
• E. Merle, B. Carluec, M. Allibert, F. Bertrand, T. Boisseau, E. Courtin, D. Heuer, A. Laureau, “Considerations on the new safety paradigm provided by liquid-fuelled reactors - Illustration on the MSFR concept”, Proceedings of the IAEA Technical Meeting on the Safety of High Temperature Gas Cooled Reactors and Molten Salt Reactors, IAEA, Vienne, Autriche (2022) - PDF version
• A. Laureau, E. Rosier, E. Merle, S. Beils, O. Bruneau, J.C. Blanchon, R. Gathmann, D. Heuer, F. Passelaigue, F. Vaiana, A. Zanini, “The LiCore Power Plant Simulator of the Molten Salt Fast Reactor”, Proceedings of the ‘PHYSOR 2020: Transition to a Scalable Nuclear Future’ International Conference, Cambridge, United Kingdom (2020) - PDF version
• S. Beils, M. Allibert, G. Campioni, B. Carluec, S. Delpech, P. Gauthé, J. Guidez, D. Heuer, A. Laureau, D. Lecarpentier, E. Merle, "Motivations and Basic Options for a Molten Salt Reactor Concept", Proceedings of the ICAPP2019 Conference, Juan les Pins, France (2019) - PDF version
• J. Guidez, E. Merle, D. Heuer, S. Bourg, G. Campioni, M. Allibert, S. Delpech, P. Gauthé, A. Laureau, J. Martinet, J. Serp, "Molten Salt Reactor to close the fuel cycle: example of MSFR multi-recycling applications", Proceedings of the ICAPP2019 Conference, Juan les Pins, France (2019) - PDF version
• J. Guidez, E. Merle, D. Heuer, S. Bourg, G. Campioni, M. Allibert, S. Delpech, P. Gauthé, A. Laureau, J. Martinet, J. Serp, "Molten Salt Reactor to close the fuel cycle: example of MSFR multi-recycling applications", Proceedings of the ICAPP2019 Conference, Juan les Pins, France (2019)
• E. Merle, M. Allibert, S. Beils, A. Cammi, B. Carluec, A. Carpignano, S. Delpech, A. Di Ronco, S. Dulla, Y. Flauw, D. Gerardin, A. Gerber, D. Heuer, A. Laureau, S. Lorenzi, M. Massone, A. Rineiski, V. Tiberi, A. C. Uggenti, “Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project”, Proceedings of the Generation IV International Forum Symposium, Paris, France (2018) - PDF version
• M. Allibert, S. Beils, G. Campioni, B. Carluec, M. Delpech, S. Delpech, P. Gauthé, D. Gerardin, A. Gerschenfeld, Y. Gorsse, J. Guidez, D. Heuer, A. Laureau, J. Martinet, E. Merle, J. Serp, “Status of current knowledge and developments in France on Molten Salt Reactors”, Proceedings of the Generation IV International Forum Symposium, Paris, France (2018)
• V.V. Ignatiev, O.S. Feynberg, M. Allibert, S. Delpech, D. Gerardin, D. Heuer, A. Laureau, E. Merle, “Molten Salt Fast Reactor in Generation IV: proliferation challenges”, Proceedings of the Symposium on International Safeguards de l’AIEA, Vienne, Autriche (2018) - PDF version
• D. Gérardin, M. Allibert, D. Heuer, A. Laureau, J. Martinet, E. Merle, “Identification and Study of Incidental an Accidental Scenarios for the Molten Salt Fast Reactor”, Proceedings of PHYTRA4 ‘Fourth International Conference on Physics and Technology of Reactors and Applications’, Marrakech, Maroc (2018) - PDF version
• D. Heuer, A. Laureau, E. Merle-Lucotte, M. Allibert, D. Gerardin, "A starting procedure for the MSFR: approach to criticality and incident analysis", Acte de conférence de la conférence internationale ICAPP’2017, Kyoto, Japon (2017) - PDF version
• D. Gérardin, M. Allibert, D. Heuer, A. Laureau, E. Merle-Lucotte, C. Seuvre, "Design Evolutions of the Molten Salt Fast Reactor", Acte de conférence soumis à l'International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation (2017) - PDF version
• A.C. Uggenti, D. Gérardin, A. Carpignano, S. Dulla, E. Merle, D. Heuer, A. Laureau, M. Allibert, “Preliminary Functional Safety Assessment for Molten Salt Fast Reactors in the framework of the SAMOFAR project”, Proceedings of the 2017 International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2017), Pittsburg, USA (2017) - PDF version
• S. Wang, M. Massone, A. Rineiski, E. Merle-Lucotte, A. Laureau, D. Gérardin, D. Heuer, M. Allibert, “A Passive Decay Heat Removal System for Emergency Draining Tanks of Molten Salt Reactors”, Actes de la conférence internationale NURETH-17, International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Xi’an, China, (2017)
• A. Laureau, M.Aufiero, P. Rubiolo,  E. Merle-Lucotte, D. Heuer,“Coupled Neutronics and Thermal-hydraulics Transient Calculations based on a Fission Matrix Approach: Application to the Molten Salt Fast Reactor”, Proceedings of the Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method, Nashville, USA (2015) - PDF version (proceedings) - PDF version (Oral Presentation - Adobe Flash Player required)
• E. Merle-Lucotte, D. Heuer, A. Laureau, M. Brovchenko, M. Allibert, M. Aufiero, P. Rubiolo,“Physical Assessment of the Load Following and Starting Procedures for the Molten Salt Fast Reactor”, Contribution 15450, Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP), Nice, France (2015) - PDF version (proceedings)
• E. Merle-Lucotte, D. Heuer, M. Allibert, M. Brovchenko, A. Laureau, V. Ghetta, P. Rubiolo, “Preliminary Design Studies of the Draining System for the Molten Salt Fast Reactor”, Proceedings of the European Nuclear Conference (ENC2014), Marseille, France (2014) - PDF version (proceedings)
• A. Laureau, P. Rubiolo, D. Heuer, E. Merle-Lucotte, M. Brovchenko, “Coupled neutronics and thermal-hydraulics numerical simulations of a Molten Salt Fast Reactor (MSFR)”, Proceedings of the Supercomputing in Nuclear Applications and Monte Carlo (SNA&MC) International Joint Conference, Paris, France (October 2013) - PDF Version (Proceedings) - PDF version (Presentation)
• P. Rubiolo, A. Laureau, E. Merle-Lucotte, M. Brovchenko, D. Heuer, “Core thermal-hydraulics analyses of the Molten Salt Fast Reactor (MSFR) in nominal conditions”, Proceedings of the Winter Meeting of the American Nuclear Society, Washington, USA (November 2013)
• E. Merle-Lucotte, M. Allibert, M. Brovchenko, D. Heuer, V. Ghetta, A. Laureau, P. Rubiolo, “Introduction to the Physics of Thorium Molten Salt Fast Reactor (MSFR) Concepts”, Actes de la conférence internationale Thorium Energy Conference 2013 (ThEC13), CERN, Genève, Suisse (2013) - PDF version (proceedings)
• M. Brovchenko, E. Merle-Lucotte, D. Heuer, A. Rineiski, “Molten Salt Fast Reactor transient analyses with the COUPLE code”, Invited papier, Proceedings of the ANS Annual Meeting "Next Generation Nuclear Energy: Prospects and Challenges", Atlanta, USA (2013) - PDF Version (proceedings)
• D. Zhang, Z.-G. Zhai, X.-N. Chen, S. Wang, A. Rineiski, “Molten Salt Fast Reactor transient analyses with the COUPLE code”, Proceedings of the ANS Annual Meeting "Next Generation Nuclear Energy: Prospects and Challenges", Atlanta, USA (2013) - PDF Version (proceedings)
• E. Merle-Lucotte, D. Heuer, M. Allibert, M. Brovchenko, V. Ghetta, P. Rubiolo, A. Laureau, “Recommandations for a demonstrator of Molten Salt Fast Reactor”, Proceedings of the International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13), Paris, France (2013) - PDF Version (proceedings) and Presentation
• P. Rubiolo D. Heuer, E. Merle-Lucotte, M. Brovchenko, V. Ghetta, M. Allibert, A. Laureau, “Overview and Perspectives of the Molten Salt Fast Reactor (MSFR) Concept”, Proceedings of the International Conference on Molten Salts in Nuclear Technology (CMSNT), Mumbai, India (January 2013) - PDF Version
• H. Boussier, S. Delpech, V. Ghetta, D. Heuer, D.E. Holcomb, V. Ignatiev, E. Merle-Lucotte, J. Serp, “The Molten Salt Reactor in Generation IV: Overview and Perspectives”, Proceedings of the Generation4 International Forum Symposium, San Diego, USA (2012) - PDF Version
• E. Merle-Lucotte, D. Heuer, M. Allibert, M. Brovchenko, V. Ghetta, A. Laureau, P. Rubiolo,“Preliminary Design Assessment of the Molten Salt Fast Reactor”, Proceedings of the European Nuclear Conference ENC2012, Manchester, UK (2012) - PDF Version (proceedings) and Presentation
• M. Brovchenko, D. Heuer, E. Merle-Lucotte, M. Allibert, N.Capellan, V. Ghetta, A. Laureau, “Preliminary Safety Calculations to Improve the Design of the Molten Salt Fast Reactor”, Proceedings of the International Conference PHYSOR 2012, LaGrange PArk, USA (2012) - PDF Version
• E. Merle-Lucotte, D. Heuer , M. Allibert , M. Brovchenko, N. Capellan, V. Ghetta,“Launching the Thorium Fuel Cycle with the Molten Salt Fast Reactor”, Contribution 11190, Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP), Nice, France (2011) - PDF Version
• E. Merle-Lucotte, D. Heuer, M. Allibert, X. Doligez, V. Ghetta,“Simulation Tools and New Developments of the Molten Salt Fast Reactor”, Contribution A0115, Proceedings of the European Nuclear Conference ENC2010, Barcelone, Espagne (2010) - PDF Version
• Véronique Ghetta, Daniel Heuer, Elsa Merle Lucotte, Xavier Doligez,“Boucle en convection forcée pour l’étude du nettoyage en ligne de caloporteurs de type sel fondu”, Contribution 0574, Actes de la conférence Matériaux 2010, Nantes, France (2010) - PDF Version (in French)
• E. Merle-Lucotte, D. Heuer, M. Allibert, X. Doligez, V. Ghetta,“Optimizing the Burning Efficiency and the Deployment Capacities of the Molten Salt Fast Reactor”, Contribution 9149, Proceedings of the International Conference Global 2009 - The Nuclear Fuel Cycle: Sustainable Options & Industrial Perspectives, Paris, France (2009) - PDF Version
• S. Delpech, E. Merle-Lucotte, T. Augé, D. Heuer,“MSFR: Material issued and the effect of chemistry control”, Proceedings of the GenerationIV International Forum Symposium, Paris, France (2009) - PDF Version
• E. Merle-Lucotte, D. Heuer, M. Allibert, X. Doligez, V. Ghetta,“Minimizing the fissile inventory of the molten salt fast reactor”, Proceedings of the International Conference Advances in Nuclear Fuel Management IV (ANFM IV), Hilton Head Island, USA (2009) - PDF Version
• S. Delpech, S. Jaskierowicz, G. Picard, E. Merle-Lucotte, D. Heuer, X. Doligez,“Innovative nuclear system based on liquid fuel”, Proceedings of the International Congress on Advances in Nuclear Power Plants ICAPP'09, Tokyo, Japan (2009) - PDF Version
• C. Renault, S. Delpech, E. Merle-Lucotte, R. Konings, M. Hron, V. Ignatiev, "The molten salt reactor: R&D status and perspectives in Europe", Actes de la conférence internationale FISA2009: 7th European Commission conference on EURATOM research and training in reactor systems, Prague, Tchéquie (2009) - PDF Version
• E. Merle-Lucotte, D. Heuer, M. Allibert, X. Doligez, V. Ghetta, C. Le Brun,“Optimization and simplification of the concept of non-moderated Thorium Molten Salt Reactor”, Proceedings of the International Conference on the Physics of Reactors PHYSOR, Interlaken (2008) - PDF Version
• D. Heuer, E. Merle-Lucotte, X. Doligez, M. Allibert,“Le réacteur à sels fondus MSFR”, Actes de la conférence Sels fondus à haute température (SELF), Presses Polytechniques et Universitaires Romandes, Chapitre 11, Aussois, France (2008) - PDF Version (in French)
• X. Doligez, D. Heuer, E. Merle Lucotte, S. Delpech, V. Ghetta, M. Allibert, G. Picard,“Thorium Molten Salt Reactor reprocessing unit: Characterization and influence on the core behaviour”, Proceedings of the Joint Symposium on Molten Salts MS8, Kobe, Japan (2008) - PDF Version
• E. Merle-Lucotte, D. Heuer, M. Allibert, V. Ghetta, C. Le Brun,“Introduction of the Physics of Molten Salt Reactor”, Proceedings of the NATO institute of advanced studies on Materials for Generation-IV Nuclear Reactors (MatGen4) (2007) - PDF Version
• E. Merle-Lucotte, D. Heuer, M. Allibert, V. Ghetta, C. Le Brun, L. Mathieu, R. Brissot, E.Liatard, “The Thorium Molten Salt Reactor: Launching the Thorium Cycle while Closing the Current Fuel Cycle”, Contribution 2.47, Proceedings of the European Nuclear Conference ENC2007, Bruxelles, Belgique (2007) - PDF Version
• E. Merle-Lucotte, D. Heuer, C. Le Brun, M. Allibert, V. Ghetta, L. Mathieu, R. Brissot, E. Liatard,“The Non-Moderated TMSR, an Efficient Actinide Burner and a Very Promising Thorium Breeder”, Proceedings of the Global2007 International Conference, La Boise, USA (2007) - PDF Version
• E. Merle-Lucotte, D. Heuer, M. Allibert, V. Ghetta, C. Le Brun, L. Mathieu, R. Brissot, E. Liatard,“Optimized Transition from the Reactors of Second and Third Generations to the Thorium Molten Salt Reactor”, Contribution 7186, Proceedings of the ICAPP (International Congress on Advances in Nuclear Power Plants), Nice, France (2007) - PDF Version
• E. Merle-Lucotte, D. Heuer, C. Le Brun, L. Mathieu, R. Brissot, E. Liatard, O. Meplan, A. Nuttin,“Fast Thorium Molten Salt Reactors started with Plutonium”, Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP), Reno, USA (2006) - PDF Version
• E. Merle-Lucotte, D. Heuer, L. Mathieu, C. Le Brun,“Molten Salt Reactor: Deterministic Safety Evaluation”, Proceedings of the European Nuclear Conference, Versailles, France (2005) PDF Version
• L. Mathieu, D. Heuer, R. Brissot, C. Garzenne, C. Le Brun, D. Lecarpentier, E. Liatard, J.M. Loiseaux, O. Méplan, E. Merle-Lucotte, A. Nuttin,“Proposal for a Simplified Thorium Molten Salt Reactor”, Proceedings of the Global 2005 International Conference, Tsukuba, Japan (2005) - PDF Version
• E. Merle-Lucotte, L. Mathieu, D. Heuer et al,“Influence of the Reprocessing on Molten Salt Reactor Behaviour”, Proceedings of the 7th International Symposium on Molten Salts Chemistry and Technology, Toulouse, France (2005) - PDF Version
• E. Merle-Lucotte, L. Mathieu, D. Heuer, J.-M. Loiseaux, A. Billebaud, R. Brissot, S. David, C. Garzenne, O. Laulan, C. Le Brun, D. Lecarpentier, E. Liatard, O. Méplan, F. Michel-Senlis, A. Nuttin, F. Perdu,“Molten Salt Reactors and Possible Scenarios for Future Nuclear Power Deployment” Proceedings of the International Conference PHYSOR 2004 - The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, USA (2004) - PDF Version
• L. Mathieu, D. Heuer, A. Nuttin, F. Perdu, A. Billebaud, R. Brissot, C. Le Brun, E. Liatard, J.-M. Loiseaux, O. Méplan, E. Merle-Lucotte, S. David, C. Garzenne, D. Lecarpentier,“Thorium Molten Salt Reactor : from high breeding to simplified reprocessing” Proceedings of the International Conference Global (2003) - PDF Version

PhD and HDR theses

• Max BEGUE, "Etude de l’impact de la turbulence sur la neutronique au sein des réacteurs a sels fondus via une modélisation couplée de la neutronique et de la mécanique des fluides", PhD Thesis, Orano and CNRS/LPSC, Université Grenoble Alpes, France (beg. 11/2023)
• Jad HALWANI, "Contributions au design et à l’évaluation des performances d’un réacteur à sels fondus de type convertisseur d’actinides", PhD Thesis, CNRS/SUBATECH and CNRS/LPSC, Université Grenoble Alpes, France (beg. 11/2023)
• Anna MAITRE, "Modélisation et étude du comportement d’un réacteur à sel fondu brûleur d’actinides en situation accidentelle", PhD Thesis, CEA Cadarache/SESI and CNRS/LPSC, Université Grenoble Alpes, France (beg. 11/2023)
• Louiliam CLOT, "Etudes de réacteurs à sels fondus de type convertisseur d’actinides et des scénarios de déploiement associés", PhD Thesis, Orano and CNRS/LPSC, Université Grenoble Alpes, France (beg. 11/2022)
• Thomas SORNAY, "Etude des effets de seuil en termes de sûreté/fonctionnement, de conception et de gestion de la matière d’un réacteur à sels fondus de type SMR en cycle du combustible U/Pu", PhD Thesis, Framatome Lyon and  CNRS/LPSC, Université Grenoble Alpes, France (beg. 11/2021)
• Hugo PITOIS, "Conception et optimisation d'un réacteur de type MSFR en sels chlorures et en cycle uranium", PhD Thesis, SAMOSAFER Euratom H2020 project, Université Grenoble Alpes, France (2023) - Manuscrit in French (version PDF)

• Thibault LE MEUTE, "Modélisation d’un scénario d’insertion de réactivité dans un réacteur à sels fondus de génération IV", PhD Thesis, CEA Cadarache/SESI et CNRS/LPSC, Université Grenoble Alpes, France (2022) - Manuscrit in French (version PDF)
• Laura MESTHIVIERS, "Étude de la capacité de conversion des actinides dans un Réacteur à Sels Fondus", PhD Thesis, ORANO et CNRS/LPSC, Université Grenoble Alpes, France (2022) - Manuscrit in French (version PDF)
• Johann MARTINET, "Mise au point et optimisation de SMR innovants de quatrième génération", PhD Thesis, Grenoble Alpes University and Framatome, France (2017-2020) - Description
• Delphine GERARDIN, "Développement d'outils numériques et réalisation d'études pour le pilotage et la sûreté du réacteur à sels fondus MSFR", PhD Thesis, Grenoble Alpes University, France (2018) - Manuscrit (in French)
• Axel LAUREAU, "Développement de modèles neutroniques pour le couplage thermohydraulique du MSFR et le calcul de paramètres cinétiques effectifs", PhD Thesis, Grenoble Alpes University, France (2015) - Manuscrit (version PDF in French) - Defense (powerpoint version in French: part 1, part 2, part 3)
  
• Mariya BROVCHENKO, "Etudes préliminaires de sûreté du réacteur à sels fondus MSFR", PhD Thesis, Grenoble Institute of Technology, France (2013) - PDF version (in french)
• Xavier DOLIGEZ, “Influence du retraitement physico-chimique du sel combustible sur le comportement du MSFR et sur le dimensionnement de son unité de retraitement”, PhD Thesis, Grenoble Institute of Technology, France (2010) - PDF Version (in French)
• Elsa MERLE-LUCOTTE, “Le cycle Thorium en réacteurs à sels fondus peut-il être une solution au problème énergétique du XXIème siècle ? Le concept de TMSR-NM”, Habilitation à Diriger les Recherches (HDR Thesis), Grenoble Institute of Technology, France (2008) - PDF Version (in French)
• Marie-Anne COGNET, “Etude préliminaire de la mesure du rapport alpha, rapport de la section efficace moyenne de capture sur celle de fission de l'233U, sur la plateforme PEREN”, PhD Thesis, Institut National Polytechnique de Grenoble, France (2007) - PDF Version (in French)
• Ludovic MATHIEU, “Cycle Thorium et Réacteurs à Sel Fondu: Exploration du champ des Paramètres et des Contraintes définissant le Thorium Molten Salt Reactor”, PhD Thesis, Institut National Polytechnique de Grenoble, France (2005) - PDF Version (in French)
• Fabien PERDU, “Titre”, PhD Thesis, Institut Polytechnique de Grenoble, France (2003) - PDF Version (in French)
• Alexis NUTTIN, “Potentialités du concept de réacteur à sels fondus pour une production durable d’énergie nucléaire basée sur le cycle thorium en spectre épithermique”, Thèse de doctorat, Université Grenoble I, France (2002) - PDF Version (in French)

Internships

• Juliette Plantier, "Modélisation du dépôt de puissance dans le réservoir de vidange d’urgence du réacteur à sels fondus de référence MSFR", LPSC/IN2P3/CNRS, stage M1/2A, mai-juillet 2023 - Rapport (PDF version)
• Kruti Mehta, "Implémentation du contrôle de la composition du combustible dans le code d’évolution SERPENT pour le réacteur à sels fondus MSFR", Subatech Nantes et LPSC Grenoble, mars-août 2022 - Description
• Thomas Sornay, "Développement d’outils pour la simulation de la physique des réacteurs à sels fondus", Master Thesis, Framatome Lyon and LPSC/CNRS, avril-septembre 2021 - Description
• Valentin Tadrent, "Amélioration du contrôle-commande du simulateur de pilotage du réacteur à sels fondus MSFR", Master 1 internship, LPSC/CNRS and CORYS TESS, mai-août 2021  - Description
• Rafaël Bellachia, "Développement du simulateur de pilotage d’un réacteur à sels fondus : Modélisation d’un compresseur et d’une turbine à détente isentropique", Master 1 internship, LPSC/CNRS et CORYS TESS, mai-juillet 2021 - Description
• Louiliam Clot, "Étude des contraintes inhérentes au déploiement massif de réacteurs à sels fondus", stage 2A/M1, LPSC/IN2P3/CNRS, mai-août 2021 - Rapport (PDF version)
• Hugo Pitois, "Convection naturelle dans le MSFR", Master Thesis, LPSC/IN2P3/CNRS, février-août 2020 - PDF version
• Laura Mesthiviers, "Etat de l’art des solutions d’incinération Pu et études neutroniques associées à certains concepts", Master Thesis, LPSC/ORANO, mars-septembre 2019
• Thibault Le Meute, "Modélisation de l’évacuation de puissance résiduelle lors du transitoire de vidange du circuit combustible d’un réacteur à sels fondus de Génération IV", Master Thesis, CEA Cadarache/SESI et CNRS/LPSC Grenoble, mars-septembre 2019 - PDF version
• Andrea Zanini, "Développement du code système du réacteur MSFR et application pour l’étude du réacteur", Master Thesis, février-juilllet 2019 - Descriptif (version pdf)
• Marceau Daronnat, "Etude de la faisabilité d'une extraction passive de la puissance résiduelle du réacteur MSFR", LPSC-IN2P3-CNRS Grenoble, avril-juin2018 - PDF version (in French)
• Florian Passelaigue, "Interfaçage du code système LiCore du réacteur MSFR sur la plateforme ALICES",  CORYS TESS/LPSC-IN2P3-CNRS, mai-août 2018 - PDF version (in French)
• Brian Sorby, "Analyse de sûreté du réacteur à sels fondus MSFR: analyse FFMEA de la couverture fertile et du circuit intermédiaire", Master 1 internship, LPSC-IN2P3-CNRS Grenoble, mai-août 2017 - PDF version (in French)
• Edouard Montanet, "Dimensionnement du réservoir de vidange d’urgence du MSFR", LPSC-IN2P3-CNRS Grenoble, avril-juin 2017 - PDF version (in French)

Other internships of interest related to the MSFR team:

• Max Bégue, "Développement et comparaison d’outils numériques pour le couplage thermohydraulique-neutronique dans les réacteurs à sels fondus", Master Thesis, Orano Project, Saint Quentin en Yvelines, april to september 2023
• Louiliam Clot, "Modélisation du recyclage des matières dans les réacteurs à sels fondus", Master Thesis, Orano, Châtillon, march-september 2022
• Thomas Sornay, "Développement d’outils pour la simulation de la physique des réacteurs à sels fondus", Master Thesis, Framatome Lyon and LPSC/CNRS, april-september 2021 - Description
• H. Pitois, "Développement de calculs de puissance résiduelle pour un concept de réacteur à neutrons rapides et à sels fondus", Subatech Nantes, april-july 2018 - PDF version (in French)

Other publications & documents on the MSFR: Generation IV International Forum (GIF)

• E. Merle-Lucotte, M. Allibert, M. Brovchenko, V. Ghetta, D. Heuer, A. Laureau, "The Concept of Fast Spectrum Molten Salt Reactor", French-Swedish Seminar on Future Nuclear Systems, Décembre 2013, Stockholm, Suède (2013) - PDF version
• J. Serp, M. Allibert, O. Beneš, S. Delpech, O. Feynberg, V. Ghetta, D. Heuer, D. Holcomb, V. Ignatiev, J.L. Kloosterman, L. Luzzi, E. Merle-Lucotte, J. Uhlíř, R. Yoshioka, D. Zhimin, “The molten salt reactor (MSR) in generation IV: Overview and Perspectives”, Prog. Nucl. Energy, 1-12 (2014) - PDF version
• Generation IV International Forum, “Annual report 2015”, MSR system pages 58-72 - PDF Version
• Generation IV International Forum, “Annual report 2014”, MSR system pages 89-102 - PDF Version
• Generation IV International Forum, “Annual report 2013”, MSR system pages 82-91 - PDF Version
• Generation IV International Forum, “Annual report 2012”, MSR system pages 97-110 - PDF Version
• H. Boussier, S. Delpech, V. Ghetta, D. Heuer, D.E. Holcomb, V. Ignatiev, E. Merle-Lucotte, J. Serp, “The Molten Salt Reactor in Generation IV: Overview and Perspectives”, Proceedings of the Generation4 International Forum Symposium, San Diego, USA (2012) - PDF Version
• Generation IV International Forum, “Annual report 2011”, MSR system pages 62-66 - PDF Version
• Generation IV International Forum, “Annual report 2010”, MSR system pages 49-55 - PDF Version
• C. Renault, S. Delpech, E. Merle-Lucotte, R. Konings, M. Hron, V. Ignatiev, "The molten salt reactor: R&D status and perspectives in Europe", Actes de la conférence internationale FISA2009: 7th European Commission conference on EURATOM research and training in reactor systems, Prague, Tchéquie (2009) - PDF Version
• Generation IV International Forum, “Annual report 2009” - PDF Version
• C. Renault, S. Delpech, E. Merle-Lucotte, R. Konings, M. Hron, V. Ignatiev, "The molten salt reactor: R&D status and perspectives in Europe", Actes de la conférence internationale FISA2009: 7th European Commission conference on EURATOM research and training in reactor systems, Prague, Tchéquie (2009) - PDF Version
• Generation IV International Forum, “Annual report 2009” - PDF Version
• C. Renault, M. Hron, R. Konings, D.E. Holcomb,“The Molten Salt Reactor (MSR) in Generation IV: Overview and Perspectives”, Actes de conférences du GIF Symposium, Paris, France (2009) - Version html
• Generation IV International Forum, “Annual report 2008” - PDF Version
• US DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum, “A Technology Roadmap for Generation IV Nuclear Energy Systems”, GIF-002-00 (2002) - PDF Version

Further information

• MSR French Bootcamp (October 4-8, 2021) in Avignon - see Trailer
• Journées Scientifiques MSR de Massy (mars 2018) and Journées CEA/DEN sur les MSR (15-16 novembre 2018 - talks) : http://irfu.cea.fr/Meetings/seminaires-MSR