Oxidation resistance of high-burnup Cr-doped UO2 accident tolerant fuel and comparison with irradiated UO2
Source abstract
Abstract
The oxidation behaviour of a high-burnup Cr-doped UO 2 fuel under dry interim storage conditions has been in-situ analysed by Raman spectroscopy. In particular, this shortest-term accident tolerant fuel (ATF) has been subjected to 350 ºC in air for about 1000 hours and its oxidation reaction compared to that of a UO 2 spent fuel irradiated in the same conditions and exposed to the same thermal treatment. The results obtained here do not only sustain the previous observation of a delay in U 3 O 8 formation in the outer periphery (rim area), compared to the pellet centre for high-burnup spent fuels, but they also prove for the first time the greater resistance of this irradiated ATF to the complete oxidation of its UO 2 matrix. These findings have been confirmed with a further test of the Cr-doped UO 2 fuel at 400 ºC, where its significant heterogeneity has been additionally noticed by the continuous acquisition of Raman spectra in different regions of the pellet.
Source: openalex_inverted_index · Quality: baseline
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Radioactive element chemistry and processing
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
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