Zircaloy cladding corrosion degradation in a tuff repository. Initial experimental plan. Revision 1
The potential for degradation or corrosion of spent fuel cladding in a tuff repository is examined, and an initial experimental plan to determine corrosion mechanisms and to estimate long-term corrosion rates is presented. The environmental history of a tuff repository at Yucca Mountain is evaluated for the potentially most severe corrosion conditions for Zircaloy spent fuel cladding. In two of the three distinct periods identified, liquid water can be present. An overview of the corrosion characteristics of zirconium and its alloys indicates that conditions in which liquid water is present should be the most corrosive conditions for spent fuel cladding. The experimental program will model the chemical, physical and geometrical aspects of spent fuel disposal as precisely as possible. The corrosion specimens will be examined by standard techniques such as optical microscopy and SEM and by state-of-the-art techniques such as using the STEM in a SEM mode to achieve much higher resolution that normally obtained with a standard SEM. A key aspect is the comparative examination that will be needed to help establish mechanisms and estimate or bound low corrosion rates. This plan presents an initial program schedule for these studies, as well as proposed schedules for the future. It also spells out what information will be provided in reports, starting at the end of FY 1985. 46 refs., 9 figs., 6 tabs.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (United States)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 59373
- Report Number(s):
- HEDL-7455-Rev.1; ON: DE85016933
- Resource Relation:
- Other Information: PBD: Jul 1985
- Country of Publication:
- United States
- Language:
- English
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