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The Effect of Low Dose Rate Radiation on the Microchemistry of 304 Stainless Steel

Published online by Cambridge University Press:  15 February 2011

T. R. Allen ,
J. I. Cole  and
E. A. Kenik
T. R. Allen
Affiliation:
Argonne National Laboratory-West, Idaho Falls, Idaho, USA
J. I. Cole
Affiliation:
Argonne National Laboratory-West, Idaho Falls, Idaho, USA
E. A. Kenik
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA
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Abstract

As part of the shutdown of the EBR-II reactor, structural materials were retrieved to analyze the effect of long term, low dose rate irradiation. In this work, the effect of low dose rate (10 to 10−9 dpa/s) irradiation on grain boundary and void surface chemistry is analyzed. These dose rates are comparable to those in light water reactor structural components. The components were irradiated at 375-379°C, temperatures near the highest temperatures experienced in pressurized water reactors. Radiation-induced segregation (RIS) was measured on samples taken from 304 stainless steel hex ducts irradiated to doses between 10 and 12 dpa. Radiation-induced segregation is shown to vary with dose rate, with measured grain boundary chromium concentrations reaching as low as 5 at. % and nickel concentrations reaching as high as 33 at. %. For some radiation conditions, significant grain boundary precipitation occurs, possibly leaving components susceptible to environmental attack.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 540: Symposium N / Microstructural Processes in Irradiated Materials , 1998 , 507
Copyright
Copyright © Materials Research Society 1999

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References

[1] Was, G. S. and Allen, T., J. Nucl. Mater. 205, 332 (1993).Google Scholar
[2] Shah, V. N. and MacDonald, P. E., Aging and Life Extension of Major Light Water Reactor Components, (Elsevier, Amsterdam, 1993).Google Scholar
[3] 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 ReactorsJekyll Island, GA, August 1989 (NACE, Houston, 1990), p. 1.Google Scholar
[4] Duysen, J. C. Van, Todeschini, P., and Zacharie, G., Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175, Kumar, A. S., Gelles, D. S., Nanstad, R., and Little, E. A., Eds., (American Society for Testing and Materials, Philadelphia, 1993), p. 747.Google Scholar
[5] Porter, D. L. and Wood, E. L., J. Nucl. Mater. 83, 90 (1979).Google Scholar
[6] Lee, E.H., Mazaisz, P.J., Rowcliffe, A.F., Phase Stability During Irradiation, Conf. Proc. edited by Holland, J.R. et al. , (TMS-AIME, NY 1981), p. 191.Google Scholar
[7] Spellward, P., Walmsley, J., Scowen, R., Partridge, N., Stump, J., Corcoran, R., Gilmour, T., Callen, V., Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Amelia Island, Fl, August 1997 (American Nuclear Society, LaGrange Park, IL, 1997), p. 734.Google Scholar
[8] Kiritani, M., Yoshiie, T., Kojima, S., Satoh, Y., and Hamada, K., J. Nucl. Mater. 174, 327 (1990).Google Scholar
[9] Garner, F. A., Sekimura, N., Grossbeck, M. L., Ermi, A. M., Newkirk, J. W., Watanabe, H., and Kiritani, M., J. Nucl. Mater. 205, 206 (1993).Google Scholar
[10] Was, G. S., Allen, T. R., Busby, J. T., Gan, J., Carter, D., Atzmon, M., and Kenik, E. A., submitted to J. Nucl. Mater.Google Scholar
[11] Carter, R. D., Damcott, D. L., Atzmon, M., Was, G. S., and Kenik, E. A., J. Nucl. Mater. 205, 361 (1993).Google Scholar
[12] Cole, J. I. and Allen, T. R., proceedings of this conference.Google Scholar
[13] Coghlan, W. A. and Garner, F. A., Radiation-Induced Changes in Microstructure: 13th International Symposium (Part 1), ASTM 955, Garner, F. A., Packan, N. H., and Kumar, A. S., Eds., (American Society for Testing and Materials,Philadelphia, 1987), p. 315.Google Scholar
[14] Dumbill, S. and Williams, T.M., in: Proceedings of the Conference on Materials for Nuclear Reactor Core Applications, Vol. 1 (BNES London 1987) p. 119 Google Scholar
[15] Williams, J. F., Spellward, P., Walmsley, J., Mager, T. R., Koyama, M., Mimaki, H., Suzuki, I., Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Amelia Island, F1, August 1997 (American Nuclear Society, LaGrange Park, IL, 1997), p. 725.Google Scholar
[16] Allen, T. R., Busby, J. T., Was, G. S., and Kenik, E. A., J. Nucl. Mater. 255,44 (1998).Google Scholar