1 Scope
This International Standard specifies common reference critical values (of which the
effective neutron multiplication factor, keff is equal to 1) for homogeneous water-moderated plutonium-uranium oxide mixtures based
on an inter-code comparison of calculated critical values.
It is applicable to operations with unirradiated mixed uranium-plutonium oxide (MOX)
outside nuclear reactors.
A classical validation approach for these systems is difficult because of the paucity
of critical experiments for MOX fuel.
Various reference systems, in terms of isotopic compositions, thicknesses of water
reflection, and densities of oxide are evaluated by different combinations of calculation
codes and nuclear data libraries (i.e. different calculation schemes, see Annex B).
The critical values defined in this International Standard are the lowest of those
calculated by each of these calculation schemes and accepted as credible.
The values in this International Standard are reference values and not absolute critical
values.