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On the Effect of Neutron Flux and Composition on Hardening of Reactor Pressure Vessel Steels and Model Alloys

Published online by Cambridge University Press:  21 March 2011

G. R. Odette
Affiliation:
Department of Mechanical and Environmental Engineering University of California, Santa Barbara Santa Barbara, CA 93106
G. E. Lucas
Affiliation:
Department of Mechanical and Environmental Engineering University of California, Santa Barbara Santa Barbara, CA 93106
D. Klingensmith
Affiliation:
Department of Mechanical and Environmental Engineering University of California, Santa Barbara Santa Barbara, CA 93106
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Abstract

Single variable experiments on a set of reactor pressure vessel and model alloys with a range of controlled compositions show a systematic effect of neutron flux (ϕ) on hardening in the intermediate fluence (ϕt) regime. The data suggest that high ϕ and enhanced recombination by vacancy trapping by solutes delays the onset of radiation-enhanced precipitation hardening.

Type
Research Article
Copyright
Copyright © Materials Research Society 2001

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References

1. Odette, G. R. and Lucas, G. E., EPRI NP 6114, Electric Power Research Institute (1989)Google Scholar
2. Odette, G. R., MRS. Symp. Proc., 373, 137 (1995).CrossRefGoogle Scholar
3. Odette, G. R. and Lucas, G. E., Rad Eff & Defects in Solids, 144, 189 (1998).CrossRefGoogle Scholar
4. Odette, G. R., Mader, E., Lucas, G. E., Phythian, W. J., English, C. A., ASTM-STP-1175, American Society for Testing and Materials, 373 (1993).Google Scholar
5. Odette, G. R., in: Neutron Irradiation Effects in Reactor Pressure Vessel Steels and Weldments, IAEA-IWG-LMNPP-98/3, Davies, M., ed., IAEA, Vienna (1998).Google Scholar
6. Odette, G. R., Lucas, G. E. Klingensmith, D., Wirth, B. D. and Gragg, D., NUREG –CR-, U. S. Nuclear Regulatory Commission, Washington D.C. (in press).Google Scholar
7. Eason, E. D., Wright, J. E. and Odette, G. R., NUREG/CR-6551, U. S. Nuclear Regulatory Commission, Washington D.C., 1998 Google Scholar
8. Stallmann, F., Wang, J. A., Kam, F. B. K., Taylor, B. J, NUREG/CR-4816, U. S. Nuclear Regulatory Commission, 1994.Google Scholar
9. Williams, T., Ellis, D., ASTM STP 1405, American Society for Testing and Materials, in press.Google Scholar

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On the Effect of Neutron Flux and Composition on Hardening of Reactor Pressure Vessel Steels and Model Alloys
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