Transient coupled calculations of the Molten Salt Fast Reactor using the Transient Fission Matrix approach

Abstract : In this paper we present transient studies of the Molten Salt Fast Reactor (MSFR). This generation IV reactor is characterized by a liquid fuel circulating in the core cavity, requiring specific simulation tools. An innovative neutronic approach called ‘‘Transient Fission Matrix” is used to perform spatial kinetic calculations with a reduced computational cost through a pre-calculation of the Monte Carlo spatial and temporal response of the system. Coupled to this neutronic approach, the Computational Fluid Dynamics code OpenFOAM is used to model the complex flow pattern in the core. An accurate interpolation model developed to take into account the thermal hydraulics feedback on the neutronics including reactivity and neutron flux variation is presented. Finally different transient studies of the reactor in normal and accidental operating conditions are detailed such as reactivity insertion and load following capacities. The results of these studies illustrate the excellent behavior of the MSFR during such transients.
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Article dans une revue
Nuclear Engineering and Design, Elsevier, 2017, 316, pp.112-124. 〈10.1016/j.nucengdes.2017.02.022〉
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Contributeur : Emmanuelle Vernay <>
Soumis le : jeudi 23 mars 2017 - 10:00:54
Dernière modification le : lundi 9 avril 2018 - 12:22:10

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A. Laureau, D. Heuer, E. Merle-Lucotte, P.R. Rubiolo, M. Allibert, et al.. Transient coupled calculations of the Molten Salt Fast Reactor using the Transient Fission Matrix approach. Nuclear Engineering and Design, Elsevier, 2017, 316, pp.112-124. 〈10.1016/j.nucengdes.2017.02.022〉. 〈in2p3-01494272〉

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