| 摘要 |
<p>PCT No. PCT/FR94/00650 Sec. 371 Date Aug. 9, 1996 Sec. 102(e) Date Aug. 9, 1996 PCT Filed Jun. 2, 1994 PCT Pub. No. WO94/29874 PCT Pub. Date Dec. 22, 1994A nuclear fuel based on UO2, ThO2 and/or PuO2 having improved retention properties for fission products. The fuel comprises a metal such as Cr or Mo able to trap oxygen in order to form an oxide having a free formation enthalpy equal to or below that of the superstoichiometric oxide or oxides (U, Th)O2+x and/or (U, Pu)O2+x (O<x</=0.01). Thus, it is possible to trap oxygen atoms released during the fission of U, Th and/or Pu. This leads to an increase in the retention level of the fission products and a possibility of obtaining a high burn-up of nuclear fuel elements.</p> |
