Published September 1997
| Version v1
Journal article
Is zirconium oxide morphology on fuel cladding largely determined by lithium hydroxide concentration effects?
Description
The oxide morphology of films on fuel cladding undergoing enhanced corrosion in BR3 is compared with laboratory observations of degradation of zirconium oxide films in concentrated LiOH solutions. It is concluded that such an LiOH concentration process could have caused the enhanced corrosion in BR3. This probably was initiated by crud deposition raising the surface temperature of the cladding above the saturation temperature during the first cycle of operation in BR3. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 249
- Journal Issue
- 1
- Journal Page Range
- p. 87-90.
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 28076063
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- BR-3 REACTOR; CLADDING; CORROSION; FUEL-COOLANT INTERACTIONS; LITHIUM HYDROXIDES; MORPHOLOGY; NUCLEAR FUELS; OXIDATION; ZIRCONIUM OXIDES
- Descriptors DEC
- ALKALI METAL COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; DEPOSITION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HYDROGEN COMPOUNDS; HYDROXIDES; LITHIUM COMPOUNDS; MATERIALS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTOR MATERIALS; REACTORS; SURFACE COATING; THERMAL REACTORS; TRANSITION ELEMENT COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM COMPOUNDS