Molten salt fast reactor

Brovchenkao, M. 2012. Preliminary Safety Calculations to Improve the Design of Molten Salt Fast Reactor. In PHYSOR 2011, BCnoxville, TN. 

Figure 7.1 Schematic representation of the reference molten salt fast reactor fuel circuit.

Figure 7.2 Calculated neutron spectrum of the reference MSFR green curve). For comparison, a typical sodium-cooled fast neutron reactor spectrum in red) and a typical PWR thermal spectrum in blue) are shown. MSFR, molten salt fast reactor SFR, sodium-cooled fast neutron reactor PWR, pressurized water reactor.

Figure 7.3 Delayed (left) and prompt (right) neutron sources in the molten salt fast reactor.

Figure 7.4 Instantaneous load-following transient of the molten salt fast reactor from an extracted power of 1.5—3 GWa, computed with the TFM-OpenFoam coupled code (Laureau et al., 2015a).

Figure 7.7 Influence of the batch reprocessing rate on the breeding ratio in the core and in the whole molten salt fast reactor system (core + fertile blanket).

Molten salt fast reactor fuel cycle scenarios... 

Figure 7.8 Time evolution up to equilibrium of the heavy nuclei inventory for the U-started MSFR (solid lines) and for the TRU-started MSFR (dashed lines). Operation time is given in equivalent full power years. MSFR, molten salt fast reactor TRU, transuranic element.

Figure 7.10 French nuclear power deployment exercise based on pressurized water reactors (PWRs), evolutionary power reactors (EPRs), and molten salt fast reactors (MSFRs).

Figure 7.14 Illustration of the main functions associated with the molten salt fast reactor operation. In the middle is the green fuel salt circuit surrounded by a pink envelope representing the first confinement barrier. The cyan envelope represents the second barrier including storing and chemical salt processing units in violet. The third barrier is in gray. Two heat transfer circuits between the three barriers are represented as loops in yellow and orange.

Figure 7.15 Residual heat in the different radioactive fluids of the molten salt fast reactor, after the total fission shutdown of the reactor previously in steady state (Brovchenko et al., 2012, 2013b). FPs, fission products.

SAMOFAR Safety assessment of MOlten salt fast reactor... 

SMART-MSFR Safety of Minor Actinides Recycling and Transmuting in Molten Salt Fast Reactor... 

Aufiero, M., Brovchenko, M., Cammi, A., Clifford, I., Geoffroy, O., Heuer, D., Laureau, A., Losa, M., Luzzi, L., Merle-Lucotte, E., Ricotti, M.E., Rouch, H., 2014. Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor anal3dical, deterministic and Monte Carlo approaches. Annals of Nuclear Energy 65, 78—90. 

Brovchenko, M., et al., 2012. Preliminary safety calculations to improve the design of molten salt fast reactor. In Proceedings of the International Conference PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tennessee, USA. 

Laureau, A., Rubiolo, P., Heuer, D., Merle-Lucotte, E., Brovchenko, M., 2013. Coupled neutronics and thermal-hydraulics numerical simulations of the molten salt fast reactor... 

Laureau, A., Aufiero, M., Rubiolo, P., Merle-Lucotte, E., Heuer, D., 2015a. Coupled neutronics and thermal-hydraubcs transient calculations based on a fission matrix approach application to the molten salt fast reactor. In 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. 

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