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Comparative Study on Intergranular Segregation of Sulfur and Phosphorus Induced During Neutron Irradiation And Thermal Ageing in Vanadium-20 WT.% Titanium Alloys

Published online by Cambridge University Press:  15 February 2011

T. E. Bloomer
Affiliation:
Ames Laboratory, Iowa State University, Ames, IA 50011
D. Y. Lyu
Affiliation:
Department of Die and Mold Design, Chonju Technical College, Chonju 560-760, Korea
J. Kameda
Affiliation:
Ames Laboratory, Iowa State University, Ames, IA 50011
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Abstract

Intergranular impurity segregation induced during neutron irradiation (9.8 × 1024 n/mr at 438 °C) and thermal ageing has been studied in V-20 wt.% Ti alloys undoped, P doped and S doped all containing residual C and O. Neutron irradiation induced intergranular segregation and desegregation of S in undoped and S doped alloys, respectively. Thermal ageing resulted in a large increase in the S segregation in the undoped and S doped alloys. However, all unirradiated, aged and irradiated P doped alloys showed negligible S segregation. The vanadium alloys had smaller P segregation, compared to the S segregation in the undoped and S doped alloys. The irradiation and ageing enhanced the P segregation in a different fashion depending on the alloys. The grain boundary enrichment of C, O and Ti was reduced during the irradiation but promoted by the thermal ageing. The underlying mechanisms controlling intergranular impurity segregation caused by irradiation or thermal ageing are discussed in light of the impurity solubility change and dynamic interaction of defect and impurity fluxes.

Type
Research Article
Copyright
Copyright © Materials Research Society 1997

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References

1. Harris, D. R., Buttermore, G. J., Hishinuma, A. and Wiffen, F. W., J. Nucl. Mater. 191, 92 (1992).Google Scholar
2. Harrod, D. L. and Gold, R. E., Inter. Metals Rev. 4, 163 (1980).Google Scholar
3. Owen, C. V., Spitzig, W. A and Bevolo, A. J., Mater. Sci. Eng. A110, 69 (1989).Google Scholar
4. Li, H., Hamilton, M. L. and Jones, R. H., Scripta Metall. et Mater. 33, 1063 (1995).Google Scholar
5. Lyu, D. Y., Bloomer, T. E., Ünal, Ö. and Kameda, J., Scripta Mater. 33, 317 (1996).Google Scholar
6. Lyu, D. Y., Bloomer, T. E., Swanson, A. H. and Kameda, J., submitted to J. Nucl. Mater,Google Scholar
7. Johnson, R.A and Lam, N. Q., Phys. Rev. B, 13, 4364 (1976).Google Scholar
8. Wiedersich, H., Okamoto, R. P. and Lam, N. Q., J. Nucl. Mater. 83, 98 (1979).Google Scholar
9. Murphy, S. M. and Perks, J. M., J. Nucl. Mater. 171, 360 (1990)Google Scholar
10. McLean, D., Grain Boundaries in Metals, Chapter V (Clarendon Press, Oxford, 1957).Google Scholar
11. King, H. W., J. Mater. Sci., 1, 79 (1966).Google Scholar
12. Kameda, J., Gold, C. R. and Bloomer, T. E., Proc. Sixth Int. Symp. on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, edited by Gold, R. E and Simonen, E. P. (TMS, Warrendall, 1993) p.531.Google Scholar
13. Seah, M. P. and Hondros, E. D., Proc. Roy. Soc., London, A335, 191 (1973).Google Scholar
14. Guttmann, M. and McLean, D., Interfacial Segregation, edited by Johnson, W. C. and Blakely, J. M. (ASM, Metal Park, OH, 1979) p. 261.Google Scholar
15. Maydet, S. L. and Russel, K. C., J. Nucl. Mater., 64, 101 (1977)Google Scholar