Science and Technology of Nuclear Installations

Research Article

Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors

Table 9

Estimated temperature of fresh and midburnup UO2-SiC fuel.
FuelFresh fuel temperature (K)Midburnup temperature (K)
UO220702306
UO2 + 10% SiC14641881
Difference (K)606425
Difference (%)29%18%
Does not account for changes in fuel-clad gap conductivity or in-pin flux depression.