MOX nuclear fuel assembly employable for a thermal neutron nuclear reactor

摘要

A MOX nuclear fuel assembly employable either for a thermal neutron reactor employing UO2 as the nuclear fuel and light water as the moderator/coolant or for a thermal neutron reactor employing the MOX fuels as the nuclear fuel and light water as the moderator/coolant is provided with only one kind of MOX nuclear fuel rods each of which has relatively large magnitude of the enrichment grade of the fissionable Pu-s or Pu<239 >and Pu<241>, the quantity of the MOX nuclear fuel rods being relatively small.