A promising fuel for fast neutron spectrum Molten Salt Reactor

NaCl-ThCl4-PuCl3

Journal article (2022)

Authors

T. Dumaire RST/Reactor Physics and Nuclear Materials - AS
J.A. Ocadiz flores RST/Reactor Physics and Nuclear Materials - AS
R. Konings European Commission Joint Research Centre, RST/Reactor Physics and Nuclear Materials - AS
A.L. Smith RST/Reactor Physics and Nuclear Materials - AS
Research Group
RST/Reactor Physics and Nuclear Materials (AS) (TU Delft)
Copyright: © 2022 T. Dumaire, J.A. Ocadiz flores, R. Konings, A.L. Smith
DOI: https://doi.org/10.1016/j.calphad.2022.102496
More Info
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Published Date

2022

Language

English

Faculty

Applied Sciences

Department

RST/Radiation, Science and Technology

Research Group

RST/Reactor Physics and Nuclear Materials

Abstract

Chloride salts are considered a good alternative to fluoride salts as fuel carrier in the Molten Salt Fast Reactor concepts. The NaCl–ThCl4–PuCl3 fuel salt solution seems very promising, with low melting temperature eutectic compositions, and the potential to be used in a breeder and burner type of reactor design. This work focuses on the first thermodynamic modeling assessment of the ThCl4–PuCl3 binary system and the NaCl–ThCl4–PuCl3 ternary system, using the CALPHAD (Computer Coupling of Phase Diagrams and Thermochemistry) method and the quasichemical formalism in the quadruplet approximation. The investigated system shows potential for a high flexibility with respect to composition at operating temperatures, which can be beneficial to accommodate the requirements on other essential fuel properties (e.g. neutronic and thermo-hydraulic).