plutonium introduces decay heat, self-irradiation and composition-sensitive thermochemical behaviour, as well as demanding radiological handling and material accountancy. isotopic composition affects heat and neutron production, so total plutonium mass alone does not specify the handling environment. The elemental metal also has inconvenient allotropic and thermal behaviour; using an appropriate stable ceramic fuel form avoids treating bare metal as a straightforward substitute for uranium oxide.
In mixed oxide fuel, plutonium dioxide and uranium dioxide form the engineered ceramic system. Important challenges are composition uniformity, thermal conductivity and melting margin, oxygen chemistry, restructuring and fission gas behaviour, and compatibility with nuclear fuel cladding. A local composition variation can produce a local power or temperature variation. During service, actinide redistribution can change the initial spatial distribution; its direction cannot be inferred from the temperature gradient alone. Autoradiographic examination of irradiated mixed-oxide pins directly investigated the competing transport effects.[ref]
Plutonium redistribution in fast reactor mixed oxide fuel pins by M. Bober and others. Journal of Nuclear Materials 47, 187–197, abstract: irradiated-pin observations, thermal diffusion, evaporation–condensation and oxygen chemistry
Mitigation is to use a characterised fuel form and isotopic inventory, qualify composition and microstructure uniformity, retain suitable thermal margins, and establish irradiation performance and interface compatibility. radioactive material confinement, remote or protected handling and waste management address the accompanying contamination and exposure problems. These are materials requirements and verification objectives; no plutonium preparation, separation or fuel-manufacturing procedure is needed to answer them.
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