Issue
EPJ Nuclear Sci. Technol.
Volume 5, 2019
Progress in the Science and Technology of Nuclear Reactors using Molten Salts
Article Number 18
Number of page(s) 11
Section Safety Evaluation
DOI https://doi.org/10.1051/epjn/2019031
Published online 11 November 2019
  1. H. Boussier et al., The Molten Salt Reactor in Generation IV: Overview and Perspectives, in Proceedings of the Generation4 International Forum Symposium, San Diego, USA , 2012 [Google Scholar]
  2. 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 77 , 308 (2014) [CrossRef] [Google Scholar]
  3. SAMOFAR Strategic Advisory Board, A paradigm Shift in Nuclear Reactor Safety with the Molten Salt Fast Reactor (SAMOFAR kick-off meeting), 2015 [Google Scholar]
  4. A. Carpignano, S. Dulla, Y. Flauw, D. Gérardin, D. Heuer, D. Lecarpentier, E. Merle, E. Ivanov, V. Tiberi, A. Uggenti, Development on an integral safety assessment methodology for MSFRs. SAMOFAR (A Paradigm Shift in Nuclear Reactor Safety with the Molten Salt Fast Reactor), European project, Work-Package WP1, Deliverable D1.5, Grant Agreement number : 661891, 2018 [Google Scholar]
  5. D. Gérardin, A. Uggenti, S. Beils, A. Carpignano, S. Dulla, E. Merle, D. Heuer, A. Laureau, M. Allibert, A methodology for the identification of the postulated initiating events of the Molten Salt fast reactor, Nucl. Eng. Technol., in press [Google Scholar]
  6. A. 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, in Proceedings of the International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2017), Pittsburgh, USA , 2017 [Google Scholar]
  7. A. Uggenti, D. Gérardin, S. Beils, A. Carpignano, S. Dulla, D. Heuer, A. Laureau, J. Martinet, E. Merle, Identification of risks and phenomena involved, identification of accident initiators and accident scenarios. SAMOFAR (A Paradigm Shift in Nuclear Reactor Safety with the Molten Salt Fast Reactor), European project, Work-Package WP1, Deliverable D1.6, Grant Agreement number : 661891, 2018 [Google Scholar]
  8. M. Allibert, D. Gérardin, D. Heuer, E. Huffer, A. Laureau, E. Merle, S. Beils, A. Cammi, B. Carluec, S. Delpech, A. Gerber, E. Girardi, J. Krepel, D. Lathouwers, D. Lecarpentier, S. Lorenzi, L. Luzzi, S. Poumerouly, M. Ricotti, M. Tiberga, V. Tiberi, Description of initial reference design and identification of safety aspects. SAMOFAR (A Paradigm Shift in Nuclear Reactor Safety with the Molten Salt Fast Reactor), European project, Work-Package WP1, Deliverable D1.1, Grant Agreement number: 661891, 2015 [Google Scholar]
  9. O. Beneš, R.J.M. Konings, Thermodynamic properties and phase diagrams of fluoride salts for nuclear applications, J. Fluorine Chem. 130 , 22 (2009) [CrossRef] [Google Scholar]
  10. O. Beneš, M. Salanne, M. Levesque, R.J.M. Konings, Physico-chemical properties of the MSFR fuel salt. EVOL (Evaluation and Viability of Liquid fuel fast reactor system) European FP7 project, Work-Package WP3, Deliverable D3.2, Contract number: 249696, 2013 [Google Scholar]
  11. Haynes international, HASTELLOY R N alloy, Marketing brochure, 2017 [Google Scholar]
  12. D. Gérardin, M. Allibert, D. Heuer, A. Laureau, E. Merle-Lucotte, C. Seuvre, Design Evolutions of the Molten Salt Fast Reactor, in Proceeding of International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russia , 2017 [Google Scholar]
  13. M.W. Rosenthal, P.R. Kasten, R.B. Briggs, Molten-salt reactors-history, status, and potential, Nucl. Appl. Technol. 8 , 107 (1970) [CrossRef] [Google Scholar]
  14. 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, Nucl. Eng. Des. 316 , 112 (2017) [CrossRef] [Google Scholar]
  15. A. Laureau, Développement de modèles neutroniques pour le couplage thermohydraulique du MSFR et le calcul de paramètres cinétiques effectifs, PhD Thesis, Grenoble-Alpes University, 2015 [Google Scholar]
  16. D. Gérardin, Développements de méthodes et outils numériques pour l'étude de la sûreté du réacteur à sels fondus MSFR, PhD Thesis, Grenoble Institute of Technology, France, 2019 [Google Scholar]
  17. M. Brovchenko, Etudes préliminaires de sûreté du réacteur à sels fondus MSFR, PhD Thesis, Grenoble Institute of Technology, France, 2013 [Google Scholar]
  18. P. Lo Pinto, L. Costes, B. Carluec, P. Quellien, S. Beils, L. Bourgue, ASTRID Safety Design: Progress on Prevention of Severe Accident, in International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russia , 2017 [Google Scholar]
  19. 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, in Proceedings of Fourth International Conference on Physics and Technology of Reactors and Applications (PHYTRA4), Marrakech, Maroc , 2018 [Google Scholar]
  20. D. Heuer, A. Laureau, E. Merle-Lucotte, M. Allibert, D. Gerardin, A starting procedure for the MSFR: approach to criticality and incident analysis, in Proceedings of the ICAPP'2017 International Conference, Kyoto, Japan , 2017 [Google Scholar]

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