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Radiation Enhanced Diffusion in Fcc Alloys*

Published online by Cambridge University Press:  16 February 2011

Wolfgang SchÜle
Wolfgang SchÜle*
Affiliation:
European Union, Institute for Advanced Materials, 1-21020 Ispra (Va), Italy and Institut für Angewandte Physik der Johann Wolfgang Goethe-Universitat Frankfurt, Robert- Mayer-Straβe 2-4, D-60054 Frankfurt am Main, Germany
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Abstract

Diffusion mechanisms in fcc materials during irradiation with high energy particles due to vacancies, interstitials, di-interstitials, and dynamic crowdions are discussed. It is shown that in most alloys an increase in the degree of order is obtained by migrating vacancies and interstitials, and only in ∝-copper-zinc alloys mainly interstitials and in nickel-chromium alloys mainly vacancies are able to increase the degree of order during irradiation. The migration activation energies of interstitials and of vacancies for these two alloys are derived.

Mass transport also by channeling and by dynamic crowdions is shown for Ni63 in nickel irradiated with 1.85 MeV electrons.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 373: Symposium Y – Microstructure of Irradiated Materials , 1994 , 267
Copyright
Copyright © Materials Research Society 1995

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Footnotes

*

The reviewer of this manuscript required an addition on his opinion according to which the majority of the people doing research on radiation damage believe in the one interstitial model. Consequently these people can not accept the point of view presented in the manuscript and the interpretation of the experimental results. The author of the present paper does not agree to these statements and he would be happy if the reviewer would give his arguments showing where the author's understanding of radiation damage and his interpretation of the results presented are wrong. There is no single experiment known to the author giving evidence for the validity of the one interstitial model.

References

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