| 摘要 |
<p>UO2, ThO2 and/or PuO2-based nuclear fuel with improved properties for retaining fission products. The fuel comprises a metal such as Cr or Mo, capable of trapping oxygen to form an oxide with a free-formation enthalpy less than or equal to that of the superstoichiometric oxide(s) (U, Th)O2+x and/or (U, Pu)O2+x (0 < x « 0,01). The oxygen atoms released during the fission of U, Th and/or Pu can thus be trapped; the fission product retention level is thereby increased and high combustion levels of the nuclear fuel elements can be attained.</p> |
