Hostname: page-component-78c5997874-8bhkd Total loading time: 0 Render date: 2024-11-19T03:47:12.459Z Has data issue: false hasContentIssue false
  • English
  • Français

Radiation-Induced Minor Element Segregation at Austenitic Stainless Steel Grain Boundaries

Published online by Cambridge University Press:  15 February 2011

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

Abstract

Measurement of minor element compositions at irradiated grain boundaries in austenitic stainless steels indicates that Si is the only element that significantly responds to radiation-induced segregation. Other minor elements, such as P or S, do not exhibit elevated grain boundary concentrations after irradiation. A rate theory evaluation of segregation is in accord with ioninduced Si enrichment, but reveals complexities in the interpretation of extrapolating behavior from ion-irradiation to neutron-irradiation behavior. The model calibrated to measured high-rate, ioninduced segregation greatly overestimates measured low-rate, neutron-irradiation segregation of Si.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 439: Symposium B – Microstructure Evolution During Irradiation , 1996 , 569
Copyright
Copyright © Materials Research Society 1997

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. Simonen, E. P. and Bruemmer, S. M., in press, J. Nucl. Mater.Google Scholar
3. Marwick, A. D., J. Phys. F, Metals Phys., 8 (1978) 1849.Google Scholar
4. Perks, J. M. and Murphy, S. M., “Modeling the Major Element Radiation-Induced Segregation in Concentrated Fe-Cr-Ni Alloys”, Proc. Materials for Nuclear Reactor Core Applications, Vol.1, BNES, London, 1987, p. 119.Google Scholar
5. Johnson, R. A. and Lam, N. Q., Phys. Rev. B13 (1976) 4364.Google Scholar
6. Rehn, L. E. and Wiedersich, H., “Solute Redistribution Under Nonequilibrium Conditions, in Surface Alloying by Ion, Electron and Laser Beams, Eds., Rehn, L. E., Picraux, S. T. and Wiedersich, H., ASM, Metals Park, OH, 1987, p. 137.Google Scholar
7. Rehn, L. E., Okamoto, P.R., Potter, D. I. and Wiedersich, H., J. Nucl. Mater., 74 (1978) 242.Google Scholar
8. Bruemmer, S. M., Chariot, L. A., and Simonen, E. P., “Measurement and Modeling of Radiation-Induced Grain Boundary Segregation in Austenitic Stainless Steel” in Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, National Association of Corrosion Engineers, 1995, p. 971.Google Scholar
9. Norris, D. I. R., Baker, C., and Titchmarsh, J. M., “Compositional Profiles at Grain Boundaries in 20%Cr/25%Ni/Nb Stainless Steel,” in Proceedings of Symposium on Radiation-Induced Sensitization of Stainless Steels held at Berkeley Nuclear Laboratories, September 1986, CEGB, INIS-GB-90, p.86.Google Scholar
10. Murphy, S. M., J. Nucl. Mater., 168 (1989) 31.Google Scholar
11. Garner, F. A. and Wolfer, W. G., J. Nucl. Mater., 102 (1981) 143.Google Scholar
12. Heinisch, H. L. and Singh, B. N., Phil. Mag. A, Vol.67, No. 2 (1993), 407.Google Scholar
13. Okamoto, P. R. and Rehn, L. E., J. Nucl. Mater., 83 (1979) 2.Google Scholar
14. Carter, R. D., Damcott, D. L., Atzmon, M., Was, G. S., Bruemmer, S. M. and Kenik, E. A., J. Nucl. Mater., 211, 70 (1994).Google Scholar