Initial report on stress-corrosion-cracking experiments using Zircaloy-4 spent fuel cladding C-rings
The Nevada Nuclear Waste Storage Investigations (NNWSI) Project is sponsoring C-ring stress corrosion cracking scoping experiments as a first step in evaluating the potential for stress corrosion cracking of spent fuel cladding in a potential tuff repository environment. The objective is to scope the approximate behavior so that more precise pressurized tube testing can be performed over an appropriate range of stress, without expanding the long-term effort needlessly. The experiment consists of stressing, by compression with a dead weight load, C-rings fabricated from spent fuel cladding exposed to an environment of Well J-13 water held at 90{degree}C. The results indicate that stress corrosion cracking occurs at the high stress levels employed in the experiments. The cladding C-rings, tested at 90% of the stress at which elastic behavior is obtained in these specimens, broke in 25 to 64 d when tested in water. This was about one third of the time required for control tests to break in air. This is apparently the first observation of stress corrosion under the test conditions of relatively low temperature, benign environment but very high stress. The 150 ksi test stress could be applied as a result of the particular specimen geometry. By comparison, the uniaxial tensile yield stress is about 100 to 120 ksi and the ultimate stress is about 150 ksi. When a general model that fits the high stress results is extrapolated to lower stress levels, it indicates that the C-rings in experiments now running at {approximately}80% of the yield strength should take 200 to 225 d to break. 21 refs., 24 figs., 5 tabs.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (United States)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 60497
- Report Number(s):
- WHC-EP-0096; ON: DE89000692
- Resource Relation:
- Other Information: PBD: Sep 1988
- Country of Publication:
- United States
- Language:
- English
Similar Records
Characterization of irradiated zircaloys: susceptibility to stress-corrosion cracking. Interim report
Corrosion test of LWR cladding tubes in high temperature seawater