Oxidative dissolution of doped UO2 and H2O2 reactivity towards oxide surfaces: A kinetic and mechanistic study
2014 (English)Licentiate thesis, comprehensive summary (Other academic)
Oxidative dissolution of std. UO2 and UO2 doped with Cr2O3 and Al2O3, i.e. ADOPT, induced by H2O2 and γ radiation has been the main focus in this licentiate thesis. The catalytic decomposition of H2O2 on oxides like Gd2O3, HfO2, CeO2, Fe2O3 and CuO were also investigated.
A kinetic study was performed by determining first and second order rate constants together with Arrhenius parameters for the decomposition of H2O2. The reactivity of H2O2 towards the oxides mentioned was observed to differ significantly despite their similarities. In the mechanistic study, the yields and dynamics of the formation of the intermediate hydroxyl radical from the decomposition of H2O2 was determined for the oxides and found to differ considerably. A turnover point could be found for most of oxides studied, i.e. an increase in the rate of hydroxyl radical scavenging after a specific amount of consumed H2O2.
The reactivity of the std. UO2 and ADOPT towards H2O2 was similar to what was observed for other UO2-based materials in previous studies. The oxidative dissolution in radiation experiments showed a slight but significant difference. This was attributed to a difference in exposed surface area instead of an effect of doping. The difference in oxidative dissolution yield was too small to be significant which supports the previous conclusion.
Leaching experiments using spent nuclear fuel were also performed on the two types of fuel showing the same behavior as the unirradiated pellets, i.e., a slightly lower 238U release from ADOPT. The difference was attributed to difference in exposed surface area. The release of fission products with low UO2 solubility displayed a higher release from ADOPT which was attributed to a difference in matrix solubility. Cs was released to a larger extent from std. UO2. This is attributed to the larger grain size of ADOPT, extending the diffusion distance. The release of lanthanides and actinides was slightly higher for the conventional UO2, nevertheless the difference was relatively small.
Place, publisher, year, edition, pages
Stockholm: KTH Royal Institute of Technology, 2014. , x, 51 p.
TRITA-CHE-Report, ISSN 1654-1081 ; 2014:23
Oxidative dissolution; UO2; ADOPT; H2O2; Spent Nuclear Fuel.
Research subject Chemistry
IdentifiersURN: urn:nbn:se:kth:diva-145691ISBN: 978-91-7595-149-2OAI: oai:DiVA.org:kth-145691DiVA: diva2:719680
2014-06-10, K2, Teknikringen 28, KTH, Stockholm, 10:00 (English)
Jonsson, Mats, Professor
QC 201405272014-05-272014-05-262014-05-27Bibliographically approved
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