Published 1987
| Version v1
Book
The influence of copper on zircaloy spent fuel cladding degradation under a potential tuff repository condition
Description
The purpose of this paper is to report the results of an experiment designed to detect the influence of copper on zircaloy spent fuel cladding degradation in a tuff repository environment. The results show that there are no indications of discrete copper-containing phases forming as part of a developing oxide film on the zircaloy and that it is estimated that it would take more than 30,000 years to penetrate the cladding by oxidation. Both metallography and the scanning electron microscope suggest that the effects of corrosion due to exposure to the model repository environment are not significant
Additional details
Publishing Information
- Publisher
- University of Arizona Nuclear Engineering Dept.
- Imprint Place
- Tucson, AZ (USA)
- Imprint Title
- Waste management '87: Waste isolation in the US, technical programs, and public education
- Journal Page Range
- p. 471-476.
Conference
- Title
- Waste management '87.
- Dates
- 1-5 Mar 1987.
- Place
- Tucson, AZ (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19079290
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COPPER; CORROSION; FUEL-CLADDING INTERACTIONS; METALLOGRAPHY; OXIDATION; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE FACILITIES; SCANNING ELECTRON MICROSCOPY; SPENT FUELS; TUFF; ZIRCALOY
- Descriptors DEC
- ALLOYS; CHEMICAL REACTIONS; ELECTRON MICROSCOPY; ELEMENTS; ENERGY SOURCES; FUELS; IGNEOUS ROCKS; MANAGEMENT; MATERIALS; METALS; MICROSCOPY; NUCLEAR FACILITIES; NUCLEAR FUELS; REACTOR MATERIALS; ROCKS; TRANSITION ELEMENTS; WASTE DISPOSAL; WASTE MANAGEMENT; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS