The influence of copper on Zircaloy spent fuel cladding degradation under a potential tuff repository condition
Conference
·
OSTI ID:60357
This paper reports the results of an experiment designed to detect the influence of copper on Zircaloy spent fuel cladding degradation in one possible repository environment. Copper and copper alloys are being considered for use in a tuff repository. The compatibility of a copper waste package container and the Zircaloy cladding on spent fuel has been questioned essentially because copper ion has been observed to accelerate zirconium alloy corrosion in acid environments, as does ferric iron, and a phenomenon called "crud-induced localized corrosion" is observed in some Boiling Water Reactors where thorugh-the-wall corrosion pits develop beneath copper-rich crud deposits. 16 refs., 6 figs., 2 tabs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States). Nevada Nuclear Waste Storage Investigations Projects Dept.
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 60357
- Report Number(s):
- UCRL-15993; HEDL-SA-3583; CONF-870306-71; ON: DE88004366
- Resource Relation:
- Other Information: PBD: Mar 1987
- Country of Publication:
- United States
- Language:
- English
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