In the present studies, the thermal behaviour of NaUO 2 BO 3 has been investigated. This compound is a potential product of interaction between the coolant (Na), control rods (B 4 C), and the oxide fuel, which could form under accidental conditions in sodium-cooled fast reactors. The thermal expansion, the heat capacity, and thermal diffusivity of NaUO 2 BO 3 have been measured. The thermal conductivity of the material is derived from these results and presented here for the first time.