Method for determining the composition of fuel salt in a molten salt reactor

Abstract

Method for determining the fuel salt composition of a molten salt reactor. This description relates to a method (300) for determining, by a computing device, the fuel salt composition of a molten salt nuclear reactor, the method comprising: - the determination of neutron fluxes (ϕ(E)) of several energies and a multiplication factor by a step of solving (302) a neutron transport equation; - the determination, for each of the nuclides, of condensed microscopic cross sections from the neutron fluxes (ϕ(E)); - the determination (303) of the weight of the nuclides on the multiplication factor from the condensed microscopic cross sections;and- the determination (304), from the weights of the nuclides, of a fuel salt supply inventory including at least one calculation of the evolution of the nuclides, by a step of solving (306) evolution equations, so that the evolution inventory respects at least one operating condition. Figure for the abstract: Fig. 3;