Patent Number: 042971683
Section: claims

1. For use in a nuclear reactor, an oxide composition nuclear fuel material in compacted pellet form containing at least one fissionable isotope and an amount of an oxide selected from the group consisting of V.sub.2 O.sub.4 and V.sub.2 O.sub.5 and mixtures thereof effective to immobilize cadmium resulting from nuclear fission chain reactions of the nuclear fuel material through a reaction between the said cadmium and the said oxide and thereby prevent cadmium embrittlement of nuclear fuel cladding at reactor operating temperatures. 2. The composition of claim 1 in which the nuclear fuel material comprises compounds selected from the group consisting of uranium oxide compounds, plutonium oxide compounds, thorium oxide compounds and mixtures thereof. 3. The composition of claim 1 in which the nuclear material comprises uranium oxide compounds. 4. The composition of claim 1 in which the immobilizing additive is V.sub.2 O.sub.5. 5. The composition of claim 1 in which the immobilizing additive is V.sub.2 O.sub.4. 6. The composition of claim 1 in which the immobilizing additive is present in the nuclear fuel in an amount between about 0.0025 and 0.025 weight percent on the basis of the nuclear material. 7. The composition of claim 1 in which the immobilizing additive-content of the nuclear fuel is about 0.0075 weight percent on the basis of the nuclear material. 8. The method of immobilizing fission product cadmium generated in nuclear fuel material of oxide composition in pellet form containing at least one fissionable isotope which comprises the step of providing in contact with the nuclear fuel material an amount of a substantially stoichiometric oxide selected from the group consisting of V.sub.2 O.sub.4 and V.sub.2 O.sub.5 and mixtures thereof effective to immobilize the cadmium generated in the nuclear fission chain reaction of the nuclear fuel material through a reaction between the said cadmium and the said vanadium oxide and thereby prevent cadmium embrittlement of nuclear fuel cladding at reactor operating temperatures. 9. The method of claim 8 in which the additive is mixed with and distributed through the nuclear fuel material. 10. The method of claim 8 in which the additive is disposed in contact with the pellet of nuclear fuel material.