Hostname: page-component-586b7cd67f-2plfb Total loading time: 0 Render date: 2024-11-29T07:22:25.054Z Has data issue: false hasContentIssue false
  • English
  • Français

Defect-Solute Interactions Near Irradiated Grain Boundaries

Published online by Cambridge University Press:  21 February 2011

E. P. Simonen ,
J. S. Vetrano ,
H. L. Heinisch  and
S. M. Bruemmer
E. P. Simonen
Affiliation:
Pacific Northwest Laboratory, P. 0. BOX 999/ P8-15, Richland, WA 99352
J. S. Vetrano
Affiliation:
Pacific Northwest Laboratory, P. 0. BOX 999/ P8-15, Richland, WA 99352
H. L. Heinisch
Affiliation:
Pacific Northwest Laboratory, P. 0. BOX 999/ P8-15, Richland, WA 99352
S. M. Bruemmer
Affiliation:
Pacific Northwest Laboratory, P. 0. BOX 999/ P8-15, Richland, WA 99352
Get access

Abstract

Defect-solute interactions control radiation-induced segregation (RIS) to interfacial sinks, such as grain boundaries, in metallic materials. The best studied system in this regard has been austenitic stainless steels. Measurements of grain boundary composition indicate that RIS of major alloying elements is in reasonable agreement with inverse-Kirkendall predictions. The steep and narrow composition profiles are shown to result from limited back diffusion near the boundary. Subsequently, defect-solute interactions that affect the near-boundary defect concentrations strongly affect RIS. The variability in measured RIS may in part be caused by grain boundary characteristics.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 319: Symposia CB – Defect-Interface Interactions , 1993 , 399
Copyright
Copyright © Materials Research Society 1994

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

1. Workshop on Solute Segregation and Phase Stability During Irradiation, edited by Stiegler, J. O., J. Nucl. Mater., 83 (1979).Google Scholar
2. Johnson, R. A. and Lam, N. Q., Phys. Rev. B, vol 13, no. 10, 4364 (1976).Google Scholar
3. Marwick, A. D., J. Phys. F, Metals Phys., 8, 1849 (1978).Google Scholar
4. Norris, D. I. R., Baker, C., and Titchmarsh, J. M., in Proceedings of Symposium on Radiation-Induced Sensitization of Stainless Steels, INIS-GB-90, ed. by Norris, D. I. R., Berkeley, Gloucestershire, GL 13 9PB, Berkeley Nuclear Laboratories, 1981, p. 86.Google Scholar
5. Simonen, E. P. and Bruemmer, S. M., in Corrosion '93 paper no. 615, National Association of Corrosion Engineers, Houston, TX., 1993.Google Scholar
6. Perks, J. M., Marwick, A. D. and English, C. A., “A Computer Code to Calculate Radiation- Induced Segregation in Concentrated Ternary Alloys,” AERE R 12121, Oxfordshire OXII ORA, Harwell Laboratory, June 1986.Google Scholar
7. Hindmarsh, A. C., GEAR: Ordinary Differential Equation System Solver, Report UCID-30001, Rev. 3, Lawrence Livermore Laboratory, Livermore, CA, 1974.Google Scholar
8. Bruemmer, S. M. and Simonen, E. P., 5, paper no. 616.Google Scholar
9. Asano, K., Fukuya, K., Nakata, K., and Kodama, M., in 5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Monterey, CA, ANS, La Grange Park, IL, 1992, p. 838.Google Scholar
10. Jacobs, A. J., Shepard, C. M., Bell, G. E. C., and Wozadlo, G. P., 9, p. 917.Google Scholar
11. Kenik, E. A., Inazumi, T., and Bell, G. E. C., J. Nucl. Mater., 183, 145 (1991).Google Scholar
12. Carter, R. D., Damcott, D. L., Atzmon, M., Was, G. S., and Kenik, E. A., J. Nucl. Mater., 205, 361 (1993).CrossRefGoogle Scholar