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Void Formation in Neutronand Ion-Irradiated Copper and Nickel

Published online by Cambridge University Press:  15 February 2011

Y. Shimomura
Affiliation:
Applied Physics and Chemistry, Faculty of Engineering, Hiroshima University, 1-4-1 Kagamiyama, Higashi-Hiroshima 739-8527, JAPAN
I. Mukouda
Affiliation:
Applied Physics and Chemistry, Faculty of Engineering, Hiroshima University, 1-4-1 Kagamiyama, Higashi-Hiroshima 739-8527, JAPAN
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Abstract

In copper which was irradiated by fission neutrons at 300°C in a temperature controlled rig to 0.0003 dpa with the damage production rate of 6 × 10−5 dpa/hr, the number of voids exceeds the number of gas atoms of hydrogen and helium which were generated by the transmutation reaction. The number density of voids was almost the same in as-received and gas-atomremoved copper which was neutron irradiated to 0.0003 dpa. These results suggest that voids can be formed by clustering of only vacancies. In 5 MeV Ni-ion irradiated copper, voids could not be observed in specimens which were irradiated between 200°C and 450°C from 0. 1 dpa to 30 dpa with the damage production rate of 6 dpa/hr. Voids were observed only in copper which was Ni-ion irradiated at 500°C. The difference of void formation on neutron-irradiation and ionirradiation is discussed. It is concluded that the production rate of damage is an important factor on the void formation in irradiated metals.

Type
Research Article
Copyright
Copyright © Materials Research Society 1999

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References

1. Zinkle, S. J., Kulcinski, G. L. and Knoll, R. W., J. Nucl. Mater. 138, 46 (1986).Google Scholar
2. Zinkle, S. J. and Farrell, K., J. Nucl. Mater. 168, 262 (1989).Google Scholar
3. Zinkle, S. J. and Lee, E. H., Metallurgical Trans. 21A, 1037 (1990).Google Scholar
4. Zinkle, S. J., Farrell, K. and Kanazawa, H., J. Nucl. Mater. 179–181, 994 (1989).Google Scholar
5. Zinkle, S. J. and Singh, B. N., J. Nucl. Mater. 199, 173 (1993).Google Scholar
6. Singh, B. N. and Zinkle, S. J., J. Nucl. Mater. 206, 212 (1993).Google Scholar
7. Zinkle, S. J. and Snead, L. L., J. Nuci. Mater. 225, 123 (1995).Google Scholar
8. Yamakawa, K., Mukouda, I. and Shimomura, Y., J. Nucl. Mater., 191–194, 396 (1992)Google Scholar
9. Mukouda, I. and Shimomura, Y., J. Nucl. Mater. in press.Google Scholar
10. Shimomura, Y., Mukouda, I. and Sugio, K., J. Nucl. Mater., 251, 61 (1997)Google Scholar
11. Ziegler, J. F and Biersack, J.P., The Stopping and Range of Ions in Solids (Pergamon Press, New York, 1985)Google Scholar
12. Katano, Y., Aruga, T., Yamamoto, S., Nakazawa, T., Yamaki, D. and Noda, K., Nucl. Instr. and Meth. in Phys. Res. B140, 152 (1998).Google Scholar
13. Mukouda, I., Shimomura, Y., Iiyama, T., Katano, Y., Yamaki, D., Nakazawa, T. and Noda, K., in this proceedings.Google Scholar
14. Greenwood, L. R. and Smither, R. K., “SPECTOR: Neutron Damage Calculations for Material Irradiations”, Argonne National Laboratory, ANL/FPP/TM-197 (1985).Google Scholar
15. Kobayashi, K., Matsushita, R., Yoshida, H., Koyama, M., Nakagawa, M., Okada, M., Kodaka, H.. Takada, J., Kozuka, T., Fujita, Y. and Kimura, I., KUR Technical Rep., KURRITR-287 (1987).Google Scholar
16. English, C. A., Eyre, B. L. and Muncie, J. W., Phil. Mag., 56, 453 (1987)Google Scholar