Characterization of vacancy type defects in irradiated UO2 and CeO2

Marc H. Weber*, J. S. McCloy, C. R. Halverson, S. E. Karcher, R. Mohun, C. L. Corkhill

*Corresponding author for this work

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

4 Citations (Scopus)

Abstract

Nuclear fuels containing uranium oxide, plus fission and activation products, will continue to undergo radioactive decay and also fission after removal from the reactor. These nuclear materials will undergo exposure to heat and persistent irradiation by alpha particles and neutrons. Vacancies and larger open volume defects, sometimes filled by helium, may be created and lead to swelling. Positron annihilation Doppler Broadening spectroscopy was implemented to investigate damage due to 1 MeV Kr-ion irradiation of UO2 and 3 MeV Au irradiation of CeO2 (a surrogate for UO2) and lanthanide-doped versions of these materials. Contrary to expectation, significant differences arose due to the doping atoms. In UO2, the doping atom type resulted in varying concentrations of the same type of defect. In CeO2, the defect type and concentration changed due to irradiation of differently doped material. Graphical abstract: Comparison of TRIM calculations to positron annihilation spectroscopy Doppler Broadening (PAS-DB) data vacancy signal S (both left axis) and PAS-DB of irradiated CeO2 (right axis). The UO2 sample was irradiated with 1 MeV Kr ions and the CeO2 sample with 3 MeV Au ions. The solid lines are the simulation of positron data (grey for UO2 from two differently prepared samples and green for CeO2) based on best fits of simple damage profiles (red). The damage profile assumes stacks of layers with constant damage. In UO2, the best fit damage shows layers of decreasing defect concentration (red). In contrast, in CeO2, the damage is low near the surface and rises. These differences may have implications for the use of CeO2 as simple non-radioactive analogue of UO2-based nuclear fuels.[Figure not available: see fulltext.]

Original languageEnglish
Pages (from-to)123-127
Number of pages5
JournalMRS Advances
Volume7
Issue number7-8
Early online date9 Feb 2022
DOIs
Publication statusPublished - Mar 2022

Bibliographical note

Publisher Copyright:
© 2022, The Author(s), under exclusive licence to The Materials Research Society.

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