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Radiation-Induced Segregation: A Microchemical Gauge to Quantify Fundamental Defect Parameters

Published online by Cambridge University Press:  16 February 2011

E. P. Simonen  and
S. M. Bruemmer
E. P. Simonen
Affiliation:
Pacific Northwest Laboratory, P. O. BOX 999/ P8-15, Richland, WA 99352
S. M. Bruemmer
Affiliation:
Pacific Northwest Laboratory, P. O. BOX 999/ P8-15, Richland, WA 99352
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Abstract

Defect kinetic parameters for radiation-induced grain boundary segregation in austenitic stainless alloys are evaluated by comparing model predictions to measured responses. Heavy-ions, neutrons, and proton irradiations having substantial statistical bases are examined. The combined modeling and measurement approach is useful for quantifying fundamental defect parameters. The mechanism evaluation indicates that vacancy migration energies were 1.15 eV or less and the vacancy formation energy at grain boundaries was 1.5 eV. Damage efficiencies of heavy ions and light-water reactor neutrons were about 0.03. Inferred proton damage efficiencies were about 0.15. Segregation measured in an advanced gas-cooled reactor component was much greater than predicted from those parameters alone.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 373: Symposium Y – Microstructure of Irradiated Materials , 1994 , 95
Copyright
Copyright © Materials Research Society 1995

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References

REFERENCES

1. Workshop on Solute Segregation and Phase Stability During Irradiation, edited by Stiegler, J. O., J. Nucl. Mater., 83 (1979).Google Scholar
2. Carter, R. D., Damcott, D. L., Atzmon, M., Was, G. S., Bruemier, S. M. and Kenik, E. A., J. Nucl. Mater., 211, 70 (1994).Google Scholar
3. 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
4. Simonen, E. P. and Bruemmer, S. M., in Corrosion '93 paper no. 615, National Association of Corrosion Engineers, Houston, TX., 1993.Google Scholar
5. 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 OX II ORA, Harwell Laboratory, June 1986.Google Scholar
6. Hindmarsh, A. C., GEAR: Ordinary Differential Equation System Solver, Report UCID- 30001, Rev. 3, Lawrence Livermore Laboratory, Livermore, CA, 1974.Google Scholar
7. Dryzek, J., Wesseling, C., Dryzek, E. and Cleff, B, Mat. Let. 21, 209 (1994).Google Scholar
8. Dimitrov, C. and Dimitrov, O., J. Phys. F: Met. Phy., 14, 783 (1984).Google Scholar
9. Dimitrov, O. and Dimitrov, C., J. Nucl. Mat. 105, 39 (1982).Google Scholar
10. Marwick, A. D., Piller, R. C. and Horton, M. E., AERE R 10895, Oxfordshire OX II ORA, Harwell Laboratory, 1983.Google Scholar
11. Rehn, L. E. and Okamoto, P. R., Mat. Sci. Forum 15–18, 985 (1987).Google Scholar
12. Naundorf, V., J. Nucl. Mater., 182, 254 (1991).Google Scholar
13. Bruemmer, S. M., Charlot, L. A. and Simonen, E. P., “Radiation-Induced Grain Boundary Segregation in Stainless Alloys, this proceedings.Google Scholar
14. Damcott, D. L., Was, G. S. and Bruemier, S. M., “Proton Irradiation Induced Grain Boundary Segregation in Austenitic Stainless Steels,” this proceedings.Google Scholar
15. Rothman, S.J., Norwicki, L.J. and Murch, G. E., J. Phys. F. Metal Phys., 10, 383 (1980).Google Scholar