Hostname: page-component-848d4c4894-pftt2 Total loading time: 0 Render date: 2024-05-21T10:45:48.038Z Has data issue: false hasContentIssue false
  • English
  • Français

Corrosion of Ticode-12 in A Simulated Waste Isolation Pilot Project (Wipp) Brine*

Published online by Cambridge University Press:  21 February 2011

T. M. Ahn ,
B. S. Lee ,
J. Woodward ,
R. L. Sabatini  and
P. Soo
T. M. Ahn
Affiliation:
Brookhaven National Laboratory, Upton, NY 11973
B. S. Lee
Affiliation:
Brookhaven National Laboratory, Upton, NY 11973
J. Woodward
Affiliation:
Brookhaven National Laboratory, Upton, NY 11973
R. L. Sabatini
Affiliation:
Brookhaven National Laboratory, Upton, NY 11973
P. Soo
Affiliation:
Brookhaven National Laboratory, Upton, NY 11973
Get access

Abstract

The corrosion behavior of TiCode-12 (Ti-0.3 Mo-0.8 Ni) high level nuclear waste container alloy has been studied for a simulated WIPP brine at a temperature of 150°C or below. Crevice corrosion was identified as a potentially important failure mode for this material. Within a mechanical crevice, a thick oxide film was found and shown to be the rutile form of TiO2, with a trace of lower oxide also present. Acidic conditions were found to cause a breakdown of the passive oxide layer. Solution aeration and increased acidity accelerate the corrosion rate. In hydrogen embrittlement studies, it was found that hydrogen causes a significant decrease in the apparent stress intensity level in fracture mechanics samples. Hydride formation is thought to be responsible for crack initiation. Stress corrosion cracking under static loads was not observed. Attention has also been given to methods for extrapolating short term uniform corrosion rate data to extended times.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 15: Symposium D – Scientific Basis for Nuclear Waste Management VI , 1982 , 761
Copyright
Copyright © Materials Research Society 1983

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

Footnotes

*

This work was performed under the auspices of the U.S. Nuclear Remulatory Commission.

References

REFERENCES

1. Braithwaite, J. W., Magnani, N. J., and Munford, J. W., “Titanium Alloy Corrosion in Nuclear Waste Environments,” SAND79–2023C, 1979.Google Scholar
2. Braithwaite, J. W. and Magnani, N. J., “Nuclear Waste Canister Corrosion Studies Pertinent to Geologic Isolation,” Nuclear and Chemical Waste Management, 1, 37 (1980).Google Scholar
3. Molecke, M. A., Schaefer, D. W., Glass, R. S., and Ruppen, J. A., “Sandia HLW Canister/Overpack Studies Applicable to a Salt Repository,” SAND81–1585, 1981.Google Scholar
4. Westerman, R. E., “Investigation of Metallic, Ceramic, and Polymeric Materials for Engineered Barrier Applications in Nuclear Waste Packages,” PNL-3484, 1980.Google Scholar
5. Pitman, S. G., “Investigation of Susceptibility of Titanium-Grade 2 and Titanium-Grade 12 to Environmental Cracking in a Simulated Basalt Repository Environment,” PNL-3914, 1981.Google Scholar
6. Dayal, R. et al. , “Nuclear Waste Management Technical Support in the Development of Nuclear Waste Form Criteria for the NRC, Task 1: Waste Package Overview,“ NUREG/CR-2333, Vol. 1, BNL-NUREG-51458, 1982.Google Scholar
7. Ahn, T. M. et al. , “Nuclear Waste Management Technical Support in the Development of Nuclear Waste Form Criteria for the NRC, Task 4: Test Development Review,” NUREG/CR-2333, Vol. 4, BNL-NUREG-51458, 1982.Google Scholar
8. Koch, G. H., Bursle, A. J., Liu, R., and Pugh, E. N., “A Comparison of Gaseous Hydrogen Embrittlement, Slow-Strain-Rate Embrittlement, and Stress Corrosion Cracking in Ti-8A1-lMo-1V,” Met. Trans. A. 12A, 1833 (1981).Google Scholar
9. “Standard Recommended Practice for Making and Using C-Ring Stress Corrosion Test Specimens,” ASTM G38–73 Annual Book of ASTM Standards, Part 10, Metals - Physical, Mechanical, and Corrosion Testing, (ASTM, Philadelphia 1979) p. 854.Google Scholar
10. Griess, J. C. Jr., “Crevice Corrosion of Titanium and Aqueous Salt Solutions,” Corrosion-NACE 24, 96 (1968).Google Scholar
11. Jackson, J. D. and Boyd, W. K., “Crevice Corrosion of Titanium,” Applications Related Phenomena in Titanium Alloys, ASTM STP 432, (ASTM, Philadelphia 1968) p. 218.Google Scholar
12. Tomashov, N. D., Chernova, G. P., Ruscol, Y. S., and Ayuyan, G. A., “The Passivation of Alloys on Titanium Bases,” Electrochemica Acta 19, 159 (1974).Google Scholar
13. “Standard Test Method for Plane-Stain Fracture Toughness of Metallic Materials,” ASTM E-399–81 Annual Book of ASTM Standards, Part 10, Metals - Physical, Mechanical, and Corrosion Testing, (ASTM, Philadelphia 1979) p. 540.Google Scholar
14. Meyn, D. A. and Sandoz, G., “Fractography and Crystallography of Subcritical Crack Propagation in High Strength Titanium Alloys,” Met. Trans. 245, 1253 (1969).Google Scholar
15. Blackburn, M. J. and Williams, J. C., Fundamental Aspects of Stress Corrosion Cracking, Staehle, R. W., Forty, A. J., and VanRooyen, D. eds. (NACE, Houston (1969) p. 620.Google Scholar
16. Moody, N. R. and Gerberich, W. W., “Hydrogen Induced Slow Crack Growth in Ti-6AI6V-2Sn,” Met. Trans. A. 11A, 973 (1981).Google Scholar
17. Meyn, D. A., paper presented at the TMS-AIME Fall Meeting in Niagra Falls, New York, September 1976.Google Scholar