Preparation, characterisation and dissolution of a CeO2 analogue for UO2 nuclear fuel

Martin C. Stennett, Claire L. Corkhill*, Luke A. Marshall, Neil C. Hyatt

*Corresponding author for this work

Research output: Contribution to journalArticle (Academic Journal)peer-review

45 Citations (Scopus)

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 UO 2 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.

Original languageEnglish
Pages (from-to)182-188
Number of pages7
JournalJournal of Nuclear Materials
Volume432
Issue number1-3
DOIs
Publication statusPublished - Jan 2013

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