In-Situ Transmission Electron Microscopy Study of the Evolution of Extended Defects in Oxide Nuclear Fuels.
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abstract
Fluorite structured actinide oxides are widely used as fuel materials in nuclear reactors. UO2, the most common nuclear fuel, is known for its high melting point and radiation tolerance [1]. ThO2 is considered a strong candidate fuel for light water reactors and advanced reactors, including molten salt breeder reactors and high temperature gas-cooled reactors. ThO2 has higher thermal conductivity and chemical stability, lower thermal expansion coefficient, and better high burn-up performance compared to UO2 [2, 3].The microstructural modifications induced by irradiation in nuclear fuels are of significant scientific and technological importance due to their impact on thermal, oxidation, and mechanical properties, affecting the overall performance and longevity of the fuels [46]. In oxide nuclear fuels, thermal conductivities can decrease by up to 70% during reactor operation. The evolution of extended defects in nuclear fuels results from a complex interplay between irradiation dose, temperature, fission products, and mechanical stresses [4, 7]. Therefore, there is a need to systematically study the impact of these parameters on defect evolution.
