Hostname: page-component-54dcc4c588-54gsr Total loading time: 0 Render date: 2025-10-08T00:06:57.279Z Has data issue: false hasContentIssue false
  • English
  • Français

Environmentally Assisted Cracking Research of Engineering Alloys for Nuclear Waste Repository Containers

Published online by Cambridge University Press:  28 March 2012

Raul B. Rebak
Raul B. Rebak*
Affiliation:
GE Global Research, Schenectady, NY 12309, USA
Get access

Abstract

All the countries that operate commercial nuclear power plants are planning to dispose of the waste in underground geologically stable repositories. The materials being studied for the fabrication of the containers include carbon steel, stainless steel, copper, titanium and nickel alloys. The aim of this work is to review results from research performed using the alloys of interest regarding their resistance to environmentally assisted cracking (EAC) under simulated repository conditions. In general, it is concluded that the environments are mild and that the studied metals may not be susceptible to cracking under the planned emplacement conditions.

Information

Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1475: Symposium NW – Scientific Basis for Nuclear Waste Management XXXV , 2012 , imrc11-1475-nw35-il10
Copyright
Copyright © Materials Research Society 2012

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.)

Article purchase

Temporarily unavailable

References

REFERENCES

1. International Atomic Energy Agency (IAEA), 2007-10-23 Press Release (iaea.org retrieved 2011 09 02) Google Scholar
2. Spadaro, J. V., Langlois, L. and Hamilton, B., “Assessing the Difference,” IAEA Bulletin 422 (iaea.org, retrieved 2011 09 02)Google Scholar
3. Rebak, R. B., “Environmental Degradation of Engineered Barrier Materials in Nuclear Waste Repositories,” Uhlig’s Corrosion Handbook, Third Edition, Edited by Winston Revie, R., John Wiley & Sons, Inc. p. 503–516 (2011)10.1002/9780470872864.ch36Google Scholar
4. Shoesmith, D. W., “Assessing the Corrosion Performance of High-Level Nuclear Waste Containers,” Corrosion Journal, Vol. 62, No. 8, pp. 703–722 (2006)10.5006/1.3278296Google Scholar
5. King, F., “Microbiologically Influenced Corrosion of Nuclear Waste Containers,” Corrosion, Vol. 65, No. 3, pp. 233–251 (2009)10.5006/1.3319131Google Scholar
6. Smart, N. R., “Corrosion Behavior of Carbon Steel Radioactive Waste Packages: A Summary Review of Swedish and U.K. Research,” Corrosion, Vol. 65, No. 3, pp. 195–212 (2009)10.5006/1.3319128Google Scholar
7. Marsh, G. P., Taylor, K. J., Bland, I. D., Westcott, C., Tasker, P. W. and Sharland, S. M., “Evaluation of the Localized Corrosion of Carbon Steel Overpacks for Nuclear Waste Disposal in Granite Environments,” in Scientific Basis for Nuclear Waste Management IX, Vol. 50, p. 421 (Materials Research Society, 1986: Warrendale, PA)Google Scholar
8. Turnbull, A., “A Review of the Possible Effects of Hydrogen on Lifetime of Carbon Steel Nuclear Waste Canisters,” NAGRA Technical Report 09–04, July 2009 (Nagra 2009: Wettingen, Switzerland).Google Scholar
9. Fukaya, Y. and Akashi, M., “Passivation Behavior of Mild Steel Used for Nuclear Waste Disposal Package,” in Scientific Basis for Nuclear Waste Management XXII, Vol. 556, p. 871 (Materials Research Society, 1999: Warrendale, PA)Google Scholar
10. Fujiwara, A., Yasutomi, I., Fukudome, K., Tateishi, T., and Fujiwara, K., “ Influence of Oxygen Concentration and Alkalinity on the Hydrogen Gas Generation by Corrosion of Carbon Steel ,” Vol. 663, p 497–505 (Materials Research Society, 2001: Warrendale, PA)Google Scholar
11. Smailos, E., “Influence of Welding and Heat Treatment on Corrosion of the Candidate High-level Waste Container Material Carbon Steel in Disposal Relevant Salt Brines,” Corrosion/2000, paper 00194 (NACE International, 2000: Houston, TX)Google Scholar
12. Terlain, A., Desgranges, C., Gauvain, D., Féron, D., Galtayries, A. and Marcus, P., “Oxidation of Materials for Nuclear Waste Containers Under Long Term Disposal,” Corrosion/2001, paper 01119 (NACE International, 2001: Houston, TX)Google Scholar
13. Féron, D., Crusset, D., and Gras, J.-M., “Corrosion Issues in the French High-Level Nuclear Waste Program,” Corrosion, Vol. 65, No. 3, pp. 213–223 (2009)10.5006/1.3319129Google Scholar
14. James, L. A. and Duncan, D. R., “Environmentally Assisted Cracking Behavior of a High-Level Nuclear Waste Container Alloy,” in Environmentally Assisted Cracking: Science and Engineering, ASTM STP 1049, Lisagor, W. B., Crooker, T. W., and Leis, B. N., Eds., American Society for Testing and Materials, Philadelphia, 1990, pp. 495–504 10.1520/STP24082SGoogle Scholar
15. Werme, L. O., “ Fabrication and Testing of Copper Canister for Long Term Isolation of Spent Nuclear Fuel ,” Vol. 608, p. 77 (Materials Research Society, 2000: Warrendale, PA)Google Scholar
16. Smith, J., Qin, Z., Shoesmith, D.W., King, F., and Werme, L., “Corrosion of Copper Nuclear Waste Containers In Aqueous Sulphide Solutions,” in Scientific Basis for Nuclear Waste Management XXIII, Vol. 824, paper CC1.12.1 (Materials Research Society, 2004: Warrendale, PA)Google Scholar
17. Worgan, K., Apted, M. and Sjöblom, R., “Performance Analysis of Copper Canister Corrosion Under Oxidizing and Reducing Conditions,” in Scientific Basis for Nuclear Waste Management XVIII, Vol. 353, p. 695 (Materials Research Society, 1995: Warrendale, PA)Google Scholar
18. Imai, H., Fukuda, T. and Akashi, M., “Effects of Anionic Species on the Polarization Behavior of Copper for Waste Package Material in Artificial Ground Water,” in Scientific Basis for Nuclear Waste Management XIX, Vol. 412, p 589–596 (Materials Research Society, 1996: Warrendale, PA)Google Scholar
19. Shoesmith, D. W., Ikeda, B. M., King, F. and Sunder, S., “Prediction of Long Term Behavior for Radioactive Nuclear Waste Disposal,” in Research Topical Symposia – Life Prediction of Structures Subject to Environmental Degradation, p. 101 (NACE International, 1996: Houston, TX)Google Scholar
20. King, F., LeNeveau, D. M. and Jobe, D. J., “Modelling the Effects of Evolving Redox Conditions on the Corrosion of Copper Containers,” in Scientific Basis for Nuclear Waste Management XVII, Vol. 333, p. 901 (Materials Research Society, 1994: Warrendale, PA)Google Scholar
21. King, F., Quinn, M. J., Litke, C. D. and LeNeveu, D. M., Corr. Sci, 37, 833 (1995)10.1016/0010-938X(95)80013-1Google Scholar
22. Honda, A., Taniguchi, N., Ishikawa, H. and Kawasaki, M., “A Modeling Study of General Corrosion of Copper Overpack for Geological Isolation of High-Level Radioactive Waste,” in Scientific Basis for Nuclear Waste Management XXII, Vol. 556, p. 911 (Materials Research Society, 1999: Warrendale, PA)Google Scholar
23. King, F., Litke, C. D. and Ikeda, B. M., “The Stress Corrosion Cracking of Copper Nuclear Waste Containers,” in Scientific Basis for Nuclear Waste Management XXII, Vol. 556, p. 887 (Materials Research Society, 1999: Warrendale, PA)Google Scholar
24. King, F., Litke, C. D. and Ikeda, B. M., “The Stress Corrosion Cracking of Copper Containers for the Disposal of High-Level Nuclear Waste,” Corrosion/99, paper 99482 (NACE International, 1999: Houston, TX)Google Scholar
25. Petterson, K. and Oskarsson, M., “Stress Corrosion Crack Growth in Copper for Waste Canister Applications,” in Scientific Basis for Nuclear Waste Management XXIII, Vol. 608, p. 95 (Materials Research Society, 2000: Warrendale, PA)Google Scholar
26. Druyts, F. and Kursten, B., “Influence of Chloride Ions on the Pitting Corrosion of Candidate HLW Overpack Materials in Synthetic Oxidized Boom Clay Water,” Corrosion/99, paper 99472 (NACE International, 1999: Houston, TX)Google Scholar
27. Fix, D. V., Estill, J. C., Hust, G. A., Wong, L. L. and Rebak, R. B., “Environmentally Assisted Cracking Behavior of Nickel Alloys in Simulated Acidic and Alkaline Waters Using U-bend Specimens,” Corrosion/2004, Paper 04549 (NACE International, 2004: Houston, TX)Google Scholar
28. Rebak, R. B., “Corrosion Testing of Nickel and Titanium Alloys for Nuclear Waste Disposition,” Corrosion, vol. 65, no4, pp. 252–271 (2009)10.5006/1.3319132Google Scholar
29. King, K. J., Wong, L. L., Estill, J. C. and Rebak, R. B., “Slow Strain Rate Testing of Alloy 22 in Simulated Concentrated Ground Waters,” Corrosion/2004, Paper 04548, (NACE International, 2004: Houston, TX)Google Scholar
30. Chiang, K. T., Dunn, D. S. and Cragnolino, G. A., “The Combined Effect of Bicarbonate and Chloride Ions on the Stress Corrosion Cracking Susceptibility of Alloy 22,” Corrosion/2006, Paper 06506, (NACE International, 2006: Houston, TX)Google Scholar
31. Zadorozne, N. S., Giordano, C. M., Carranza, R. M., and Rebak, R. B., “Anodic behavior of nickel alloys in media containing bicarbonate and chloride ions,” Corrosion/2012, NACE International (Houston, TX)Google Scholar
32. Shoesmith, D. W. and Ikeda, B. M., “Development of Modeling Criteria for Prediction Lifetimes of Titanium Nuclear Waste Containers,” in Scientific Basis for Nuclear Waste Management XVII, Vol. 333, p. 893 (Materials Research Society, 1994: Warrendale, PA)Google Scholar
33. Akashi, M., Nakayama, G. and Fukuda, T., “Initiation Criteria for Crevice Corrosion of Titanium Alloys Used for HLW Disposal Overpack,” Corrosion/98, paper 98158 (NACE International, 1999: Houston, TX)Google Scholar
34. Nakayama, G., Murakami, K. and Akashi, M., “Assessment of Crevice Corrosion and Hydrogen Induced Stress Corrosion Cracks of Ti-Pd Alloys for HLW Overpack in Deep Underground Water Environments,” in Scientific Basis for Nuclear Waste Management XXVI, Vol. 757, p 771–778 (Materials Research Society, 2003: Warrendale, PA)Google Scholar
35. Nakamura, N., Akashi, M., Fukaya, Y., Nakayama, G. and Ueda, H., “Stress-Corrosion Crack Initiation Behavior in a-Titanium Used for Nuclear Waste Disposal Overpack,” Corrosion/2000, paper 00195 (NACE International, 2000: Houston, TX)Google Scholar
36. Hua, F., Mon, K., Pasupathi, P., Gordon, G., and Shoesmith, D., JOM, January, pp. 20–26 (2005).10.1007/s11837-005-0059-4Google Scholar
37. Ikeda, B. M. and Quinn, M. J., “ Hydrogen Assisted Cracking of Grade-16 Titanium: A Preliminary Examination of Behaviour at Room Temperature ,” 06819-REP-01200–0039 R00 (Toronto, Ontario, Canada: Ontario Hydro, 1998)Google Scholar
38. Clarke, C. F., Hardie, D., and Ikeda, B. M., “Hydrogen-Induced Cracking of Commercial Purity Titanium,” Corrosion Science, 39 (9) (1997), pp. 1545–1559 10.1016/S0010-938X(97)00055-3Google Scholar
39. Gordon, G. M., Corrosion, 58, 811 (2002)10.5006/1.3287662Google Scholar
40. Schutz, R. W., “Platinum Group Metal Additions to Titanium: A Highly Effective Strategy for Enhancing Corrosion Resistance,” Corrosion, 59, 1043 (2003)10.5006/1.3277524Google Scholar
41. Hua, F., Mon, K., Pasupathi, P., Gordon, G. M. and Shoesmith, D. W., “Corrosion of Ti Grade 7 and Other Ti Alloys in Nuclear Waste Repository Environments – A Review,” Corrosion/2004, Paper 04698 (NACE International, 2004: Houston, TX)Google Scholar
42. Brossia, C. S. and Cragnolino, G. A., “Effects of Environmental and Metallurgical Conditions on the Passive and Localized Dissolution of Ti-0.15%Pd,” Corrosion, 57, 768 (2001)10.5006/1.3280611Google Scholar
43. Wong, L. L., Estill, J. C., Fix, D. V. and Rebak, R. B., “Corrosion Characteristics of Titanium Alloys in Multi-Ionic Environments,” PVP-Vol. 467, 63 (ASME, 2003: New York, NY)Google Scholar
44. Young, L. M., Catlin, G. M., Gordon, G. M. and Andresen, P. L., “Constant Load SCC Initiation Response of Alloy 22 (UNS N06022), Titanium Grade 7 and Stainless Steels at 105°C,” Corrosion/2003, Paper 03685 (NACE International, 2003: Houston, TX)Google Scholar
45. Fix, D. V., Estill, J. C, Wong, L. L. and Rebak, R. B., “Susceptibility of Welded and Non-Welded Titanium Alloys to Environmentally Assisted Cracking in Simulated Concentrated Ground Waters,” Corrosion/2004, Paper 04551 (NACE International, 2004: Houston, TX)Google Scholar