Nuclear fuel with improved retention properties of fission products.

摘要

The invention relates to a nuclear fuel based on UO2, ThO2 and / or PuO2 having improved properties of retention of fission products. BR/ This fuel comprises a metal such as Cr or Mo, capable of trapping oxygen to form an oxide having a free enthalpy of formation less than or equal to that of the overstoichiometric oxide (s) (U , Th) O2 + x and / or (U, Pu) O2 + x (0 Thus, we can trap the oxygen atoms released during the fission of U, Th, and / or Pu; this results in an increase in retention rate of fission products and the possibility of achieving high burnup rates of nuclear fuel elements.