Published 2013
| Version v1
Miscellaneous
The role of fission products (noble metal particles) in spent fuel corrosion process in a failed container
Creators
- 1. Univ. of Western Ontario, Dept. of Chemistry, London, Ontario (Canada)
- 2. Univ. of Western Ontario, Surface Science Western, London, Ontario (Canada)
Description
The corrosion/dissolution of simulated spent fuel has been studied electrochemically. Fission products within the UO2 matrix are found to have significant effect on the anodic dissolution behaviour of the fuel. It is observed that H2O2oxidation is accelerated on the surfaces of doped noble metal (ε) particles existing in the fuel matrix. It is concluded that H2O2 decomposition rather than UO2 corrosion should be the dominant reaction under high H2O2 concentrations. (author)
Availability note (English)
Available as a slide presentationAdditional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 978-1-926773-13-1
- Imprint Title
- Nuclear the next generation. 34th Annual Canadian Nuclear Society conference and 37th CNS/CNA student conference
- Imprint Pagination
- 78 Megabytes
- Journal Page Range
- [5 p.]
Conference
- Title
- 34. Annual Canadian Nuclear Society conference; 37. CNS/CNA student conference
- Dates
- 9-12 Jun 2013
- Place
- Toronto, Ontario (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 47120198
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CORROSION; DISSOLUTION; ELECTROCHEMISTRY; FISSION PRODUCTS; SPENT FUELS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; CHEMISTRY; ENERGY SOURCES; FUELS; ISOTOPES; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 11 refs., 2 figs.