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Dose Dependence of Radiation Induced Segregation in Proton Irradiated Austen1tic Alloys

Published online by Cambridge University Press:  15 February 2011

J. T. Busby
Affiliation:
The University of Michigan, Department of Nuclear Engineering and Radiological Sciences Ann Arbor. MI 48109.
T. R. Allen
Affiliation:
The University of Michigan, Department of Nuclear Engineering and Radiological Sciences Ann Arbor. MI 48109.
R. D. Carter
Affiliation:
The University of Michigan, Department of Nuclear Engineering and Radiological Sciences Ann Arbor. MI 48109.
E. A. Kenik
Affiliation:
Metal and Ceramics Division, Oak Ridge National Laboratory Oak Ridge, TN 37831
G. S. Was
Affiliation:
The University of Michigan, Department of Nuclear Engineering and Radiological Sciences Ann Arbor. MI 48109.
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Abstract

The dose dependence of radiation-induced segregation (RIS) is investigated for proton irradiated ultra high-purity (UHP) 304L stainless steel and Fe-20Cr-24Ni. Grain boundary compositions were measured in samples irradiated with 3.2 MeV protons at 400°C to doses ranging from 0.1 to 3.0 dpa. RIS measurements were made using scanning transmission electron microscopy with energy dispersive x-ray spectroscopy (STEM/EDS) and compared to results from Auger electron spectroscopy (AES). Comparison of the dose dependence for HP-304L and Fe- 20Cr-24Ni shows that RIS is alloy specific. The approach to steady-state Cr depletion was observed to be more rapid in the alloy with higher Ni content. Fe-2OCr-24Ni reaches a steady-state Cr depletion level by 0.5 dpa, and the amount of Cr depletion in HP-304L SS is still increasing between 1.0 and 3.0 dpa. RIS in the stainless steel alloys irradiated with 3.2 MeV protons is comparable to that in neutron irradiated steels of similar composition.

Type
Research Article
Copyright
Copyright © Materials Research Society 1997

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References

[1] Was, G.S. and Andresen, P., J.Metals 44 (4) (1992) 8.Google Scholar
[2] Allen, T.R., Was, G.S., Kenik, E.A., accepted in J. Nucl. Mater.Google Scholar
[3] Damcott, D.L., Allen, T.R., and Was, G.S., J. Nucl. Mater., 225 (1995) 97107.Google Scholar
[4] Damcott, D.L., Cookson, J.M., Rotberg, V.H., and Was, G.S., Nucl. Inst. and Meth. in Phys. Res. B, 99 (1995) 780783.Google Scholar
[5] Damcott, D.L., Cookson, J.M., Carter, R.D. Jr., Martin, J.R., Atzmon, M., and Was, G.S., Radiat. Eff. Def. Solids, 118 (1991) 383.Google Scholar
[6] Allen, T. R., Damcott, D. L., Was, G. S., and Kenik, E. A.,Proceedings of the Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE International, Houston, TX, 1995, 997 Google Scholar
[7] Allen, T.R., Cookson, J.M., Damcott, D.L., and Was, G.S., these proceedings.Google Scholar
[8] Carter, R.D., Damcott, D.L., Atzmon, M., Was, G.S., Bruemmer, S.M., and Kenik, E.A., J. Nucl. Mater., 211 (1994) 70.Google Scholar
[9] Jacobs, A.J., Proc. 16th Int. Symp. on Radiation on Materials, ASTM-STP 1175 eds. Kumar, A.S., Gelles, D.S., Nanstad, R.K. and Little, E.A. (American Society for Testing Materials, Philadelphia, 1993) 902.Google Scholar
[10] Norris, D.I.R., Baker, C., Taylor, C., and Titchmarsh, J.M., Proc. 15th Int. Symp. On Radiation on Materials, ASTM-STP 1125 eds. Kumar, A.S., Gelles, D.S., Nanstad, R.K. and Little, E.A. (American Society for Testing Materials, Philadelphia, 1992) 603.Google Scholar
[11] Perks, J.M., Marwick, A.D., and English, C.A., AERE R 12121, June 1986.Google Scholar