Hostname: page-component-77c89778f8-7drxs Total loading time: 0 Render date: 2024-07-18T15:14:52.520Z Has data issue: false hasContentIssue false
  • English
  • Français

Effect of Bulk Phosphorus Content on Hardening, Non-Equilibrium Segregation and Embrittlement in Neutron Irradiated Iron-Based Alloys

Published online by Cambridge University Press:  21 March 2011

Y. Nishiyama ,
T. E. Bloomer  and
J. Kameda
Y. Nishiyama
Affiliation:
Japan Atomic Energy Research Institute, Ibaraki, Japan
T. E. Bloomer
Affiliation:
Ames Laboratory, Iowa State University, Ames IA, USA Presently, U.S. Nuclear Regulatory Commission, Washington DC
J. Kameda
Affiliation:
Ames Laboratory, Iowa State University, Ames IA, USA Office of Naval Research International Field Office, Tokyo, Japan
Get access

Abstract

The effect of bulk P contents on hardening, non-equilibrium intergranular segregation and embrittlement has been studied in Mn-doped ferritic alloys subjected to neutron irradiation (E>0.1MeV: fluence of 1 × 1025 n/m2 at 711K for 2120 h) or irradiation-equivalent thermal aging. Neutron irradiation-induced intergranular P segregation became more prominent with decreasing bulk P content. Thermal aging slightly enhanced the amount of segregated P independent of the bulk P content. Intergranular C segregation in all the alloys was suppressed by the irradiation. An alloy with low bulk P content showed only moderate irradiation-induced hardening. The ductile-brittle transition temperature (DBTT) in alloys with low and intermediate amounts of P increased by the same shift during the irradiation but not at all during the thermal aging. Doping high bulk P led to a high DBTT in the as-heat-treated alloy while the irradiation decreased the DBTT. The irradiation effect on the DBTT in the model ferritic alloys containing the different levels of P is discussed in light of embrittling or toughening effects caused by the changes in the P or C segregation, and hardness.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 650: Symposium R – Microstructural Processes in Irradiated Materials-2000 , 2000 , R6.10
Copyright
Copyright © Materials Research Society 2001

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1. Phythian, W. J. and English, C. A., J. Nucl. Mater., 205, 162 (1993).Google Scholar
2. Okamoto, P. R. and Rehn, L. E., J. Nucl. Mater., 83, 2 (1993).Google Scholar
3. Murphy, S. M., Perks, J. M., J. Nucl. Mater., 171, 360 (1990).Google Scholar
4. Kameda, J. and Bevolo, A. J., Acta Metall., 37, 3283 (1989).Google Scholar
5. Kameda, J. and Mao, X., Mater. Sci. & Eng., A112, 143 (1989).Google Scholar
6. Kameda, J. and Bloomer, T. E., Acta Mater., 47, 893 (1999).Google Scholar
7. Kameda, J., Gold, C. R. and Bloomer, T. E. Proc. Sixth Inter. Sym. Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, edited by Gold, R. E., Simonen, E. P., TMS, Warrendale, (1994) p. 531.Google Scholar
8. Kameda, J., Nishiyama, Y. and Bloomer, T. E., Surf. Inter. Analy., in press.Google Scholar
9. Erhart, H. and Grabke, H. J., Metal Sci., 15, 401 (1981).Google Scholar
10. Seah, M. P. and Hondros, E. D., Proc. Royal Soc., London, A375, 191 (1973).Google Scholar
11. Guttmann, M. and McLean, D., Interfacial Segregation, edited by Johnson, C. and Blakely, J.M. American Society of Materials: Metal Park, (1979) p.261.Google Scholar
12. Maydet, S. L. and Russell, K. C., J. Nucl. Mater., 64, 101 (1977).Google Scholar
13. Phythian, W. J., Vatter, I. A., Dumbill, S. and Kameda, J., unpublished work.Google Scholar
14. Kameda, J., Acta Metall., 34, 2391 (1986).Google Scholar