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Graphite Disk UO2 Fuel Elements Designed for Extended Burnups at High Powers

Roderick D. MacDonald, Ian J. Hastings

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 430-444

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33696

Zircaloy-clad fuel elements containing UO2 pellets separated by thin graphite disks have been irradiated to maximum burnups of 800 MWh/kg U (33 000 MWd/tonne U) at a linear power range of 30 to 70 kW/m. Fission gas release and sheath strains were lower than experienced for conventional fuel under comparable conditions because of the lower bulk average fuel temperatures in disk elements. The irradiated disk elements also showed good internal stability, tolerance to power ramping, and acceptable defect behavior.