Thermal property change of MOX and UO2 irradiated up to high burnup of 74GWd/t

Thermal Energy Transport in Oxide Nuclear Fuel

“…Recommended values of A0 and B for pristine samples of UO2, ThO2, and CeO2 are summarized in Table 1 and representative conductivity profiles as a function of temperature are shown in Figure 24. The simplified formulation, and minor variations thereof, has been used to describe the thermal conductivity of fresh and irradiated UO2 fuel [538,539], mixed uranium-plutonium dioxide (MOX) fuel [540,541,542], and rare-earth doped UO2 [543].…”

“…In particular, A can be represented as A = A 0 + ∑ i x i A i ′ , where the summation is over defects i , x i is the concentration of defect i , A i ′ is the scattering parameter for defect i , and A 0 is the residual value for a pristine material. , Recommended values of A 0 and B for pristine samples of UO 2 , ThO 2 , and CeO 2 are summarized in Table , and representative conductivity profiles as functions of temperature are shown in Figure . The simplified formulation and minor variations thereof have been used to describe the thermal conductivity of fresh and irradiated UO 2 fuel, , mixed uranium–plutonium dioxide (MOX) fuel, − and rare-earth-doped UO 2 …”