Analysis of the Fuel-Loop Characteristics of a Molten-Salt Nuclear Reactor with a Cavity Core

Аннотация

Thermohydraulic validation is a priority for the ZhSR-S [MOSART] molten-salt nuclear transmuter for transuranium elements from the spent nuclear fuel of solid-fuel thermal reactors. In the present article, the results of coupled neutronics and thermohydraulics calculations, based on which the configuration of the cavity core and fuel loop were chosen, are generalized. The thermohydraulic validation of such a reactor was preceded by the development of an experimental database on the physical properties of the fuel salt with the molar composition 73LiF–27BeF₂ + AnF₃ and 58NaF–15LiF–27BeF₂ + AnF₃. The optimized 2400 MW(t) ZhSr-S core satisfies the two most important requirements of thermohydraulics: no recirculation or stagnant zones and quite low maximum temperature of the solid reflectors so that they can be used for a long time.