De Bona E, Popa K, Walter O, Cologna M, Hennig C, Scheinost AC, Prieur D. Oxidation of Micro- and Nanograined UO
2 Pellets by In Situ Synchrotron X-ray Diffraction.
Inorg Chem 2022;
61:1843-1850. [PMID:
35044161 PMCID:
PMC9052414 DOI:
10.1021/acs.inorgchem.1c02652]
[Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
Abstract
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When in contact with oxidizing media,
UO2 pellets used
as nuclear fuel may transform into U4O9, U3O7, and U3O8. The latter
starts forming by stress-induced phase transformation only upon cracking
of the pristine U3O7 and is associated with
a 36% volumetric expansion with respect to the initial UO2. This may pose a safety issue for spent nuclear fuel (SNF) management
as it could imply a confinement failure and hence dispersion of radionuclides
within the environment. In this work, UO2 with different
grain sizes (representative of the grain size in different radial
positions in the SNF) was oxidized in air at 300 °C, and the
oxidation mechanisms were investigated using in situ synchrotron X-ray
diffraction. The formation of U3O8 was detected
only in UO2 pellets with larger grains (3.08 ± 0.06
μm and 478 ± 17 nm), while U3O8 did
not develop in sintered UO2 with a grain size of 163 ±
9 nm. This result shows that, in dense materials, a sufficiently fine
microstructure inhibits both the cracking of U3O7 and the subsequent formation of U3O8. Hence,
the nanostructure prevents the material from undergoing significant
volumetric expansion. Considering that the peripheral region of SNF
is constituted by the high burnup structure, characterized by 100–300
nm-sized grains and micrometric porosity, these findings are relevant
for a better understanding of the spent nuclear fuel behavior and
hence for the safety of the nuclear waste storage.
The present work reports on the oxidation behavior of UO2 disks having equal density but different grain size (3.08
μm, 478 nm, and 163 nm). After 21 h at 300 °C under air,
the first two samples transformed into U3O8,
while only U3O7 could be detected in the third
one. This finding is relevant for nuclear waste management, since
the grain size of the high burnup structure is comparable to that
of the third sample.
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