Hostname: page-component-586b7cd67f-dlnhk Total loading time: 0 Render date: 2024-11-29T07:50:48.566Z Has data issue: false hasContentIssue false
  • English
  • Français

Origin and Influence of Pre-Existing Segregation on Radiation-Induced Segregation In Austenitic Stainless Steels

Published online by Cambridge University Press:  15 February 2011

E. A. Kenik ,
J. T. Busby ,
M. K. Miller ,
A. M. Thuvander  and
G. Was
E. A. Kenik
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831-6376, [email protected]
J. T. Busby
Affiliation:
University of Michigan, Ann Arbor, MI 48109
M. K. Miller
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831-6376
A. M. Thuvander
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831-6376
G. Was
Affiliation:
University of Michigan, Ann Arbor, MI 48109
Get access

Abstract

The pre-existing segregation at grain boundaries in two austenitic stainless steels has been investigated by atom probe field ion microscopy and analytical electron microscopy. In addition, the effect of radiation-induced segregation on the near-grain-boundary composition has been studied by analytical electron microscopy. Pre-existing enrichment of Cr, Mo, B, C and P and depletion of Fe and Ni near grain boundaries has been observed. Significant affinity between Mo and N in both alloys is indicated by the detection of MoN2+` molecular ions during field evaporation. The pre-existing segregation is modified by radiation-induced segregation resulting in Ni and Si enrichment near the boundary as well as depletion of chromium adjacent to the boundary resulting in a “W-shaped” Cr profile.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 540: Symposium N / Microstructural Processes in Irradiated Materials , 1998 , 445
Copyright
Copyright © Materials Research Society 1999

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. Asano, K. et al. , Fifth International Symposium On Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, pp. 836–46, American Nuclear Society (1991).Google Scholar
2. Walmsley, J. et al. , Seventh International Symposium On Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, pp. 985–94, NACE International (1995).Google Scholar
3. Kenik, E. A., J. Nucl. Mater. 187 (1992) 239–46.Google Scholar
4. Dumbill, S., Ph.D. Thesis, University of Birmingham, U.K. (1992).Google Scholar
5. Jacobs, A. J., Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175, pp. 902–18 (1993).Google Scholar
6. Kenik, E. A. and Burke, M. G., Proc. 50th Electron Microscopy Society of America, pp.1214–15, San Francisco Press (1992).Google Scholar
7. Busby, J. et al. , this proceedings.Google Scholar
8. Lundin, L. and Andren, H-O., Appl. Surf. Sci., 94/951 (1996) 320 Google Scholar
9. Thomson, R. C. and Miller, M. K., Acta Mater. 46 (1998) 2203–13.Google Scholar