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MÖssbauer Study of Zircaloy After Neutron Irradiation at Power Reactor Temperatures

Published online by Cambridge University Press:  16 February 2011

Jerzy A. Sawicki
Jerzy A. Sawicki*
Affiliation:
AECL Research, Chalk River Laboratories, Chalk River, Ontario, KOJ IJO, Canada
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Abstract

57Fe-Mössbauer spectroscopy was used to examine a specimen of Zircaloy-4 from a pressure tube extracted from a high-flux fuel channel of a CANDU* reactor. During 25 years of service the alloy was exposed to a fast-neutron fluence of 5.6×1021 n/cm2. The obtained spectra of unirradiated and neutron-irradiated specimens differ considerably. This is attributed to the radiation-induced dissolution and crystalline-to-amorphous transformation of Zr(Cr,Fe)2 precipitates, accompanied by reprecipitation and partial recrystallization of metastable Zr2Fe particles in the zirconium matrix. The correspondence between Mtssbauer and electron microscopy observations, as well as the similarity between neutron-irradiated and ion-implanted specimens, is discussed.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 373: Symposium Y – Microstructure of Irradiated Materials , 1994 , 215
Copyright
Copyright © Materials Research Society 1995

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References

REFERENCES

1. Gilbert, R.W., Griffiths, M. and Carpenter, G.J.C., J. Nucl. Mater. 135, 265 (1985).Google Scholar
2. Yang, W.J.S., Tucker, R.P., Cheng, B. and Adamson, R.B., J. Nucl. Mater. 138, 185 (1986).Google Scholar
3. Griffiths, M., Gilbert, R.W. and Carpenter, G.J.C., J. Nucl. Mater. 150, 53 (1987).Google Scholar
4. Griffiths, M. and Gilbert, R.W., J. Nucl. Mater. 150, 169 (1987).Google Scholar
5. Yang, W.J.S., J. Nucl. Mater. 158, 71 (1988).Google Scholar
6. Yang, W.J.S. and Adamson, R.B., in Zirconium in Nuclear Industry: Eight International Symposium. ASTM STP 1023, eds. Swam, L.F.P. and Eucken, C.M. (ASTM, Philadelphia, 1989) pp. 451–477.Google Scholar
7. Etoh, Y. and Shimada, S., J. Nucl. Mater. 200, 56 (1993).Google Scholar
8. Griffiths, M., J. Nucl. Mater. 159, 190 (1988); J. Nucl. Mater. 170, 294 (1990).Google Scholar
9. Griffiths, M., Chow, C.K., Coleman, C.E., Holt, R.A., Sagat, S. and Urbanic, V.F., in 16th International Symposium on Effects of Irradiation on Materials, Denver, Colorado, 1992.Google Scholar
10. Coleman, C.E., Cheadle, B.A., Causey, A.R., Chow, P.C.K., Davies, P.H., McManus, M.D., Rodgers, D.K., Sagat, S. and Drunen, G. Van, in Zirconium in Nuclear Industry: Eighth International Symposium, ASTM STP 1023, eds. Swam, L.F.P. and Eucken, C.M. (ASTM, Philadelphia, 1989) pp. 35–49.Google Scholar
11. Sawicki, J.A., Hood, G.M., Zou, H. and Schultz, R.J., J. Nucl. Mater. (1994), in press.Google Scholar
12. Aubertin, F., Gonser, U., Campbell, S.J. and Wagner, H-G., Z. Metalkunde 76, 237 (1985).Google Scholar
13. Sawicka, B.D., Letocha, E., Sawicki, J.A., Tyliszczak, T. and Binczycka, H., Phys. Lett. A 100, 45 (1984).Google Scholar
14. Sawicki, J.A., Mater. Sci. and Eng. 69, 501 (1985).Google Scholar
15. Sawicka, B.D. and Sawicki, J.A., Nucl. Instr. Meth. 209/210, 799 (1983).Google Scholar
16. Yoshida, Y., Menningen, M., Sielemann, R., Vogl, G., Weyer, G. and Schröder, K., Phys. Rev. Lett. 61, 195 (1988).Google Scholar
17. Vincze, I., Woude, F. van der and Scott, M.G., Sol. State Comm. 37, 567 (1981).Google Scholar
18. Howing, W., Woude, F. van der, Bushow, K.H.J. and Vincze, I., J. Non-Cryst. Solids 61–62, 421 (1984).Google Scholar
19. Howing, W., Scholte, P.M.L.O., Derenbos, P., Fokkema, G.A., Weits, E.A.G., Woude, F. van der, Vincze, I. and Bushow, K.H.J., Phys. Rev. 32, 8368 (1985).Google Scholar
20. Motta, A.T. and Olander, D.R., Acta Metall. Mater. 38, 2174 (1990).Google Scholar
21. Kai, J.J., Huang, W.I. and Chou, H.Y., J. Nucl. Mater. 170, 193 (1990).Google Scholar
22. Lefebvre, F. and Lemaignan, C., J. Nucl. Mater. 165, 122 (1989).Google Scholar
23. Howe, L.M., Phillips, D., Motta, A.T. and Okamoto, P.R., Surf. Coat. Tech. 66 (1994) 411.Google Scholar
24. Nelson, R.S., Hudson, J.A. and Mazey, D.J., J. Nucl. Mater. 44, 318 (1972).Google Scholar
25. Motta, A.T. and Lemaignan, C., J. Nucl. Mater. 195, 27 (1992).Google Scholar