Irradiation of zirconolite ceramic wasteform for plutonium disposition

An alternative approach is the conditioning of the UK-owned Pu stockpile via immobilisation within a ceramic matrix. Zirconolite ceramic designed for plutonium disposition, which contains 2M and 4M structure, was irradiated by 5 MeV Au ion at DCF. The amorphisation and morphology of the pristine and irradiated sample were compared. The partial amorphisation and swelling were evidenced after irradidation. Overall, no cracking was observed. It was revealed that radiation tolerance appears to vary with respect to zirconolite polytype. The initial results suggests zirconolite-2M phase may have a better radiation tolerance than 4M. Further investigation within amorphous layer and interface region is ongoing to clarify these early findings.


If you would like to leave a comment then please login and/or register. If you are logged in and seeing this message it is because we have not received the acknowledgement of your email address yet.