Hostname: page-component-77c89778f8-5wvtr Total loading time: 0 Render date: 2024-07-24T18:11:27.688Z Has data issue: false hasContentIssue false
  • English
  • Français

Evaluation of the Possible Susceptibility of Titanium Grade 7 to Hydrogen Embrittlement in a Geologic Repository Environment

Published online by Cambridge University Press:  21 March 2011

Charles A. Greene ,
Alvin J. Henry ,
C. Sean Brossia  and
Tae M. Ahn
Charles A. Greene
Affiliation:
US Nuclear Regulatory Commission, Mail Stop T-7C6, Washington, DC 20555-0001, USA
Alvin J. Henry
Affiliation:
Previously at US Nuclear Regulatory Commission, MPR Associates, 320 King Street, Alexandria, VA 22314, USA
C. Sean Brossia
Affiliation:
Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, 6220 Culebra Road, San Antonio, TX 78238, USA
Tae M. Ahn
Affiliation:
US Nuclear Regulatory Commission, Mail Stop T-7C6, Washington, DC 20555-0001, USA
Get access

Abstract

Ti grade 7 has been selected by the U.S. DOE as the current material of choice for the drip shield in the proposed high level waste (HLW) repository design. Due to the addition of Pd, Ti grade 7 exhibits enhanced resistance to hydrogen embrittlement (HE), yet there is relatively little data on HE of this material. Calculations of hydrogen absorption/recombination, solubility, and free energy of hydride formation in Ti and Pd are presented to qualitatively evaluate Keff, the stress intensity factor for crack propagation induced by hydride formation, of Ti grade 7 in relation to other Ti alloys without Pd. Calculations were performed that show concentration of hydrogen in Ti grade 7 may exceed the critical hydrogen concentration, Hc, where the material becomes embrittled, when accelerated passive dissolution of Ti grade 7 in concentrated Cl- and Cl-+F- solutions as the source of hydrogen is considered.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 663: Symposium – Scientific Basis for Nuclear Waste management XXIV , 2000 , 515
Copyright
Copyright © Materials Research Society 2001

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.)

References

REFERENCES

1. Harrington, P., 119th Meeting Advisory Committee on Nuclear Waste, June 2000, Washington, DC: U.S. Nuclear Regulatory Commission.Google Scholar
2.U.S. Department of Energy, Repository Safety Strategy: Plan to Prepare the Postclosure Safety Case to Support Yucca Mountain Site Recommendation and Licensing Considerations, TDRWIS-RL-000001 REV 03. Washington, DC: U.S. Department of Energy, Office of Civilian Radioactive Waste Management (2000).Google Scholar
3. Schutz, R. W. and Thomas, D. E., Corrosion of Titanium and Titanium Alloys, ASM Handbook, Vol 13, Materials Park, OH: ASM International (1987) 669–706.Google Scholar
4. Schutz, R. W., Stress Corrosion Cracking of Titanium Alloys, Stress Corrosion Cracking Materials Performance and Evaluation, Materials Park, OH, ASM International (1992) 265–297.Google Scholar
5. Brossia, C. S., Cragnolino, G. A., Effects of Environmental, Electrochemical and Metallurgical Variables on the Passive and Localized Dissolution of Ti Grade 7, Proceedings of the Corrosion 2000 Conference, Paper No. 211, Houston, TX, NACE International (2000).Google Scholar
6. Gute, G. D., Ghosh, A., Hsiung, S. M. and Chowdhury, A. H., Assessment of Mechanical Response of Drip Shields Under Repository Environment -- Progress Report, IM 20.01402.671.070, San Antonio, TX: Center for Nuclear Waste Regulatory Analyses (2000).Google Scholar
7. Kerrisk, J. F., Groundwater Chemistry at Yucca Mountain, Nevada, and Vicinity. LA-10929-MS. Los Alamos, NM: Los Alamos National Laboratory (1987).Google Scholar
8. Harrar, J. E., Carley, J. F., Isherwood, W. F., and Raber, E., Report of the Committee to Review the Use of J-13 Well Water in Nevada Nuclear Waste Storage Investigations (1990).Google Scholar
9. Shoesmith, D. W., Hardie, D., Ikeda, B. M. and Noel, J. J., Hydrogen Absorption and Lifetime Performance of Titanium Waste Containers, AECL-11770. Pinawa, Manitoba, Canada: Atomic Energy of Canada Limited (1997).Google Scholar
10. Lu, S. C., Hydrogen Induced Cracking of Drip Shield Analysis Model Report - Draft, ANLEBS-MD-000006 Rev 00, Chicago, IL: Argonne National Laboratory (2000).Google Scholar
11. Shoesmith, D. W., Review of the Expected Behavior of Alpha Titanium Alloys Under Yucca Mountain Conditions - Draft, AECL-12089, TDR-MGR-SE-000002 Rev 00, (2000).Google Scholar
12. Brossia, C. S., Cragnolino, G. A., Effects of Environment and Metallurgical Condition on the Passive and Localized Dissolution of Ti-0.15Pd, Submitted for Publication to Corrosion Journal (2000).Google Scholar
13. Gordon, Gerald. “Stress Corrosion Cracking (SCC) and Hydrogen Induced Cracking (HIC): Modeling and Experimental Program Status” Department of Energy presented at CLST Appendix 7 Meeting, Lawrence Livermore National Laboratory, July 7-8, (1999).Google Scholar
14. , Park et al. Journal of Nuclear Materials. vol 220–222 (1995) 827–31.Google Scholar
15. , Doyle, Journal of Nuclear Materials. vol. 111 & 112 (1982) 628–35.Google Scholar
16. , Moody and , Gerberich. “Solubility Considerations for threshold stress intensities controlled by hydride fracture” Scripta Metullurgica, vol 15 (1981) 709–711.Google Scholar
17. Simpson, L. A. and Puls, M. P., Metallurgical Transactions, Vol 10A (1979) 1093.Google Scholar
18. McQuillian, A. D., Metallurgy of Titanium, in Lianov, et. al., New York (1956).Google Scholar
19.Hydrogen in Titanium, Daniel Davey and Company, NY (1965) 47.Google Scholar
20.ASM Handbook, vol 3: Alloy Phase Diagrams. ASM International, Materials Park, OH (1992) 2,314, 2,237-8.Google Scholar
21. , Volkl and , Alefeld. AHydrogen Diffusion in Metals@ in Diffusion in Solids, (1975) 248.Google Scholar
22. Reilly, J., “Chemistry of Intermetallic Hydrides” Brookhaven National Laboratory (1991).Google Scholar
23. Tsujikawa, S. and Kojima, Y., Crevice Corrosion-NaCl Concentration Map for Grade-2 Titanium at Elevated temperature, Scientific Basis for Nuclear Waste Management XVI, Interrante, C. G. and Pabalan, R. T., eds., Pittsburgh, PA: Materials Research Society: Symposium Proceedings: 294: (1998) 311–316.Google Scholar
24. Ikeda, B. M., Bailey, M. G., Cann, D. C., and Shoesmith, D. W., Effect of Iron Content and Microstructure on the Crevice Corrosion of Grade-2 Titanium Under Nuclear Waste Vault Conditions, Advances in Localized Corrosion NACE-9, Houston, TX: NACE International (1990) 439–444.Google Scholar
25. Shridhar, N., Cragnolino, G. A., Dunn, D. S., and Manaktala, H. K., 1994, Review of Degradation Modes of Alternate Container Materials, CNWRA 94-010, San Antonio, TX: Center for Nuclear Waste Regulatory Analyses (1994).Google Scholar
26. Farmer, J., McCright, R. D., General Corrosion and Localized Corrosion of the Drip Shield Analysis Model Report - Draft, ANL-EBS-MD-000004 Rev 00, Chicago, IL: Argonne National Laboratory (2000).Google Scholar
27. Ikeda, B. M., Quinn, M. J., Hydrogen Assisted Cracking of Grade-16 Titanium: A Preliminary Examination of Behavior at Room Temperature, 06819-REP-01200-0039 R00, 1.13, Toronto, Ontario: Atomic Energy of Canada Ltd. (1998).Google Scholar
28. Meyn, D. A., U.S. Naval Research Laboratory Memorandum Report 2461, Washington, DC, June (1972).Google Scholar
29. Gdowski, G. E., Degradation Mode Survey Candidate Titanium-Base Alloys for Yucca Mountain Project Waste Package Materials, Lawrence Livermore National Laboratory, December (1997).Google Scholar
30. Tomashov, N. D., et al. “Corrosion and Passivitiy of the Cathode-Modified Titanium-based Alloys” Titanium and Titanium Alloys, Vol 2, Plenum Press, NY (1982) 915–25.Google Scholar