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Preparation,characterisation and dissolution of a CeO2 analogue for UO2 nuclear fuel
Authors:Martin C Stennett  Claire L Corkhill  Luke A Marshall  Neil C Hyatt
Affiliation:1. Metallurgical and Materials Engineering, Colorado School of Mines, Golden, CO, USA;2. Fuel Cycle and Isotopes Division, Oak Ridge National Laboratory, Oak Ridge, TN, USA;3. Nuclear Fuels and Materials Division, Idaho National Laboratory, Idaho Falls, ID, USA;4. Fuel Performance and Development, Idaho National Laboratory, Idaho Falls, ID, USA;2. Argonne National Laboratory, South Cass Avenue, Argonne, IL 60493, USA;1. Materials Science and Engineering Department, University of Florida, Gainesville, FL, USA;2. Mechanical Engineering Department, University of Florida, Gainesville, FL, USA;1. State Key Laboratory Cultivation Base for Nonmetal Composite and Functional Materials, Southwest University of Science and Technology, Mianyang 621010, China;2. National Defense Key Discipline Lab of Nuclear Waste and Environmental Safety, Southwest University of Science and Technology, Mianyang 621010, China
Abstract:The behaviour of spent nuclear fuel under geological conditions is a major issue underpinning the safety case for final disposal. This work describes the preparation and characterisation of a non-radioactive UO2 fuel analogue, CeO2, to be used to investigate nuclear fuel dissolution under realistic repository conditions as part of a developing EU research programme. The densification behaviour of several cerium dioxide powders, derived from cerium oxalate, were investigated to aid the selection of a suitable powder for fabrication of fuel analogues for powder dissolution tests. CeO2 powders prepared by calcination of cerium oxalate at 800 °C and sintering at 1700 °C gave samples with similar microstructure to UO2 fuel and SIMFUEL. The suitability of the optimised synthesis route for dissolution was tested in a dissolution experiment conducted at 90 °C in 0.01 M HNO3.
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