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Effect of Formation and Growth of Dislocation Loops and Cavities on Low-Temperature Swelling of Irradiated Uranium-Molybdenum Alloys*

Published online by Cambridge University Press:  15 February 2011

J. Rest ,
G. L. Hofman ,
I. I. Konovalov  and
A. A. Maslov
J. Rest
Affiliation:
Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439, USA
G. L. Hofman
Affiliation:
Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439, USA
I. I. Konovalov
Affiliation:
Bochvar Institute, Rogov St. 5, 123060 Moscow, Russia
A. A. Maslov
Affiliation:
Bochvar Institute, Rogov St. 5, 123060 Moscow, Russia
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Abstract

Scanning electron photomicrographs of U–10 wt.% Mo irradiated at low temperature in the Advanced Test Reactor (ATR) to about 40 at.% burnup show the presence of cavities. We have used a rate-theory-based model to investigate the nucleation and growth of cavities during low-temperature irradiation of uranium-molybdenum alloys in the presence of irradiation-induced interstitial-loop formation and growth. Our calculations indicate that the swelling mechanism in the U–10 wt.% Mo alloy at low irradiation temperatures is fission-gas driven. The calculations also indicate that the observed bubbles must be associated with a subgrain structure. Calculated bubble-size-distributions are compared with irradiation data.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 540: Symposium N / Microstructural Processes in Irradiated Materials , 1998 , 609
Copyright
Copyright © Materials Research Society 1999

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Footnotes

*

Work supported by U.S. Department of Energy, Office of Arms Control and Nonproliferation, under Contract W–31–109-Eng-38.

References

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