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Radiation-Induced Segregation in 316 and 304 Stainless Steels Irradiated at Low Dose Rate

Published online by Cambridge University Press:  21 March 2011

T. R. Allen ,
J. I. Cole ,
J. Ohta ,
K. Dohi ,
H. Kusanagi ,
E. A. Kenik  and
Oak Ridge
T. R. Allen
Affiliation:
Argonne National Laboratory-West
J. I. Cole
Affiliation:
Argonne National Laboratory-West
J. Ohta
Affiliation:
Central Research Institute of Electric Power Industry
K. Dohi
Affiliation:
Central Research Institute of Electric Power Industry
H. Kusanagi
Affiliation:
Central Research Institute of Electric Power Industry
E. A. Kenik
Affiliation:
National Laboratory
Oak Ridge
Affiliation:
National Laboratory
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Abstract

As part of the shutdown of the EBR-II reactor, structural materials were retrieved to analyze the effects of long-term irradiation on mechanical properties and microstructure. In this work, the effect of low dose rate irradiation (10−7 to 10−8 dpa/s) on grain boundary composition in 316 and 304 stainless steels was analyzed. Samples were taken from surveillance specimens and subassemblies irradiated in the reflector region of EBR-II at temperatures from 371-390°C to maximum doses of 30 dpa. The effects of dose, dose rate, and bulk composition on radiation- induced segregation are analyzed. In 316 stainless steel, changes in grain boundary chromium and nickel concentrations occur faster than changes in iron and molybdenum concentrations. In 304 stainless steel, decreasing the dose rate increases the amount of grain boundary segregation. For a dose of 20 dpa, chromium depletion and nickel enrichment are greater in 304 stainless steel than in 316 stainless steel, the difference most likely due to dose rate. In both 304 and 316 stainless steels, the presence of a grain boundary precipitate significantly changes the composition of the adjacent grain boundary.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 650: Symposium R – Microstructural Processes in Irradiated Materials-2000 , 2000 , R2.4
Copyright
Copyright © Materials Research Society 2001

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References

REFERENCES

1. Andresen, P.L., Ford, F.P., Murphy, S.M., and Perks, J.M., Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Jekyll Island, GA, August 1989 (NACE, Houston, 1990), p. 1.Google Scholar
2. Was, G. S., Allen, T. R., Busby, J. T., Gan, J., Damcott, D., Carter, D., Atzmon, M., and Kenik, E. A., J. Nucl. Mater., 270, 96 (1999).Google Scholar
3. Simonen, E. P. and Bruemmer, S. M., Proceedings of the MRS Fall Meeting Symposium Y: Microstructure of Irradiated Materials, Edited by Robertson, I. M., Rehn, L. E., Zinkle, S. J., Phythian, W. J., (Mater. Res. Soc. Proc. 373, Pittsburgh, PA, 1995) pp. 95.Google Scholar
4. Walmsley, J., Spellward, P., Fisher, S., and Jenssen, A., Proc. Seventh Int. Symp. on Env. Deg. of Materials in Nuclear Power Systems-Water Reactors, Edited by Gold, R.E and Simonen, E.P, Breckenridge, CO (1995), p. 985.Google Scholar
5. Perks, J.M., Marwick, A.D., and English, C.A., AERE R 12121 June 1986.Google Scholar
6. Allen, T. R., Busby, J. T., Was, G. S., and Kenik, E. A., Effects of Radiation on Materials, 19th International Symposium, ASTM STP 1366, Edited by Hamilton, M. L., Kumar, A. S., Rosinski, S. T., and Grossbeck, M. L., (American Society for Testing and Materials, 1999).Google Scholar
7. Allen, T. R., Cole, J. I., Dietz, N. L., Wang, Y., Was, G. S., and Kenik, E. A., proceedings of this conference.Google Scholar
8. Cookson, J. M., Damcott, D. L., Was, G. S., and Andresen, P. L., Proc. Sixth Int. Symp. on Env. Deg. Mat Nucl Power Syst Water React Proceedings of the 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, San Diego, CA (1993), p. 573.Google Scholar