Change search
ReferencesLink to record
Permanent link

Direct link
Oxidative dissolution of ADOPT compared to standard UO2 fuel
KTH, School of Chemical Science and Engineering (CHE), Chemistry, Applied Physical Chemistry.
KTH, School of Chemical Science and Engineering (CHE), Chemistry, Applied Physical Chemistry.ORCID iD: 0000-0003-0663-0751
(English)Manuscript (preprint) (Other academic)
URN: urn:nbn:se:kth:diva-145720OAI: diva2:720003

QS 2014

Available from: 2014-05-27 Created: 2014-05-27 Last updated: 2014-05-27Bibliographically approved
In thesis
1. Oxidative dissolution of doped UO2 and H2O2 reactivity towards oxide surfaces: A kinetic and mechanistic study
Open this publication in new window or tab >>Oxidative dissolution of doped UO2 and H2O2 reactivity towards oxide surfaces: A kinetic and mechanistic study
2014 (English)Licentiate thesis, comprehensive summary (Other academic)
Abstract [en]

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.
National Category
Chemical Sciences
Research subject
urn:nbn:se:kth:diva-145691 (URN)978-91-7595-149-2 (ISBN)
2014-06-10, K2, Teknikringen 28, KTH, Stockholm, 10:00 (English)

QC 20140527

Available from: 2014-05-27 Created: 2014-05-26 Last updated: 2014-05-27Bibliographically approved

Open Access in DiVA

No full text

Search in DiVA

By author/editor
Nilsson, KristinaJonsson, Mats
By organisation
Applied Physical Chemistry

Search outside of DiVA

GoogleGoogle Scholar
The number of downloads is the sum of all downloads of full texts. It may include eg previous versions that are now no longer available

Total: 39 hits
ReferencesLink to record
Permanent link

Direct link