Hostname: page-component-7bb8b95d7b-qxsvm Total loading time: 0 Render date: 2024-09-12T17:41:20.971Z Has data issue: false hasContentIssue false

Corrosion and Stress Corrosion Cracking of Alloy 22 in Lead-Containing Solutions

Published online by Cambridge University Press:  11 February 2011

Yi-Ming Pan
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA), Southwest Research Institute, 6220 Culebra Road, San Antonio, TX 78238–5166, USA
Darrell S. Dunn
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA), Southwest Research Institute, 6220 Culebra Road, San Antonio, TX 78238–5166, USA
Leitai Yang
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA), Southwest Research Institute, 6220 Culebra Road, San Antonio, TX 78238–5166, USA
Gustavo A. Cragnolino
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA), Southwest Research Institute, 6220 Culebra Road, San Antonio, TX 78238–5166, USA
Get access

Abstract

The susceptibility of Alloy 22 to localized corrosion and stress corrosion cracking was evaluated in lead-containing solutions. Speciation calculations indicate that aqueous dissolution of PbCl2 resulted in the formation of Pb2+ and Pb-Cl complexes. PbCl2 was selected among several lead compounds for its high solubility and dissociation rate. The total dissolved lead species concentration was measured by inductively coupled plasma-atomic emission spectrometry. Comparative anodic polarization tests were conducted in a range of deaerated, acidified PbCl2 solutions. The presence of lead species in a super-saturated PbCl2 solution with apH of 0.5 promotes the occurrence of apronounced anodic peak and significantly increases the passive current density. Enhanced dissolution of Alloy 22 resulted, as characterized by the presence of randomly distributed etch pits. At an applied potential of -100 mVSCE, which is the potential corresponding to the anodic peak, Alloy 22 was found to be resistant to stress corrosion cracking when tested in super-saturated PbCl2 solutions (pH 0.5) at 95 °C [203 °F]. Moreover, no deleterious effect of lead species on localized corrosion was observed in crevice specimens over a wide range of lead concentrations with the exception of acidified, super-saturated PbCl2 solutions. Provided that these high lead concentrations are not attainable in the anticipated repository environments, Alloy 22 is unlikely to be susceptible to stress corrosion cracking or localized corrosion.

Type
Research Article
Copyright
Copyright © Materials Research Society 2003

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. Copson, H.R. and Dean, S.W., Corrosion 21, 18 (1965).Google Scholar
2. Agrawal, A.K. and Paine, J.P.N., Proc. of the Fourth Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems—WaterReactors (NACEIntl., Houston, TX, 1990) pp. 7–1 to 7–17.Google Scholar
3. Helie, M., Lambert, I., and Santarini, G., Proc. of the Seventh Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors (NACE Intl., Houston, TX, 1995) pp. 247258.Google Scholar
4. Carlos, B.A., Chipera, S.J., and Bish, D.L., Distribution and Chemistry of Fracture-Lining Minerals at Yucca Mountain, Nevada, LA–12977–MS (Los Alamos National Laboratory, Los Alamos, NM, 1995).Google Scholar
5. Perfect, D.L., Faunt, C.C., Steinkampf, W.C., and Turner, A.K., Hydrochemical Data Base for the Death Valley Region, California and Nevada, Open-File Report 94–305 (U.S. Geological Survey, Denver, CO, 1995).Google Scholar
6. Pulvirenti, A.L., Needham, K. M., Adel-Hadadi, M. A., Marks, C. R., Gorman, J. A., and Barkatt, A., Scientific Basis for Nuclear Waste Management XXV, Mcgrail, B.P. and Cragnolino, G.A., eds. (Mater. Res. Soc. Proc. 713, Warrendale, PA, 2002) pp. 8995.Google Scholar
7. Estill, J.C., King, K.J., Fix, D.V., Spurlock, D.G., Hurst, G.A., Gordon, S.R., Mccright, R.D., and Rebak, R.B., Corrosion 2002, Paper No. 535 (NACE Intl., Houston, TX, 2002).Google Scholar
8. Helgeson, H.C., Kirkham, D.H., and Flowers, G.C., American Journal of Science 281, 12491516 (1981).Google Scholar
9. Bromley, L.A., Journal of Chemical Thermodynamics 4, 669673 (1972).Google Scholar
10. Pitzer, K.S., Journal of Physical Chemistry 77, 268277 (1973).Google Scholar
11. Pitzer, K.S., Activity Coefficients in Electrolyte Solutions, Pitzer, K.S., ed. (CRC Press, Boca Raton, FL, 1991) pp. 75153.Google Scholar
12. Dunn, D.S., Pan, Y.-M., and Cragnolino, G.A., Corrosion 2000, Paper No. 206 (NACE Intl., Houston, TX, 2000).Google Scholar
13. ASTM Standard Test Method G61–86. Annual Book of ASTM Standards. Vol. 03.02 (ASTM Intl., West Conshohocken, PA, 2001).Google Scholar
14. ASTM Standard Practice G30–97. Annual Book of ASTM Standards. Vol. 03.02 (ASTM Intl., West Conshohocken, PA, 2001).Google Scholar
15. Pan, Y.-M., Brossia, C.S., Cragnolino, G.A., Dunn, D.S., Gute, G.D., and Yang, L., Stress Corrosion Cracking and Hydrogen Embrittlement of Container and Drip Shield Materials, CNWRA Report 2002 (CNWRA, San Antonio, TX, 2002).Google Scholar
16. Ives, M.B., Localized Corrosion (NACE–3, NACE Intl., Houston, TX, 1974) pp. 78103.Google Scholar
17. Sakai, T., Aoki, K., Shigemitsu, T., and Kishi, Y. Corrosion 48, 745750 (1992).Google Scholar
18. Costa, D., Talah, H., Marcus, P., Calvar, M., and Gelpi, A., Proc. of the Seventh Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors (NACE Intl., Houston, TX, 1995) pp. 199208.Google Scholar