Hostname: page-component-848d4c4894-8bljj Total loading time: 0 Render date: 2024-07-05T10:32:11.032Z Has data issue: false hasContentIssue false

An Ion Beam Simulation of the Swelling of U3Si

Published online by Cambridge University Press:  26 February 2011

Charles W. Allen
Affiliation:
Materials Science Division Argonne National Laboratory, Argonne, IL 60439, USA
Robert C. Birtcher
Affiliation:
Materials Science Division Argonne National Laboratory, Argonne, IL 60439, USA
Lynn E. Rehn
Affiliation:
Materials Science Division Argonne National Laboratory, Argonne, IL 60439, USA
Gerard L. Hofman
Affiliation:
Materials and Components Technology Division Argonne National Laboratory, Argonne, IL 60439, USA
Get access

Abstract

Uranium intermetallics are under consideration as possible low-enrichment reactor fuels. These materials divide into two classes with regard to dimensional stability during their service lifetime: those which suffer extreme dimensional growth and those which do not. It has been suggested that the rapid-swelling materials are those that become glassy under irradiation while the low-swelling materials are those that remain crystalline. The structural and dimensional stabilities of U3Si (depleted uranium) have been investigated as a function of temperature duning Kr irradiation by in situ. HVEM observations. Below 550 K, this material becomes glassy during 1.0 MeV Kr irradiation. Prolonged irradiation at 475 K also leads to rapid darkening of the TEM bright field image of the specimen, growth of the initial perforation at rates which far exceed those due to sputtering, and formation of additional thin areas and holes. Irradiation at 615 K does not result in observable image darkening or rapid growth of the initial perforation. After 2×1020 Kr m-2, the crystalline material irradiated at 615 K is stabilized against subsequent ion-irradiation-induced amorphization and growth at 475 K. Similarly, after 2×1020 Kr m-2 at 475 K, the glassy phase persists at 620 K under additional Kr irradiation, and the rapid growth continues. The mechanism of the irradiation-induced growth of the glassy material does not involve gas precipitation but rather may involve deformation by viscous flow assisted by the defects generated during irradiation.

Type
Research Article
Copyright
Copyright © Materials Research Society 1988

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

[1] Hofman, G. L., J. Nucl. Mater. 140 (1986) 256.Google Scholar
[2] Walker, D. G. and Morel, P.A., J. Nucl. Mater. 39 (1971) 49.Google Scholar
[3] Cartz, L. and Fournelle, R. A., Rad. Eff. 41 (1979) 211.Google Scholar
[4] Cartz, L., Karioris, F. G. and Fournelle, R. A., Rad. Eff. 54 (1981) 57.CrossRefGoogle Scholar
[5] Klaumünzer, S. and Schumacher, G., Phys. Rev. Lett. 51 (1983) 1987.Google Scholar
[6] Klaumünzer, S., Schumacher, G., Hou, Ming-dong and Vogl, G., Proceedings of the Fifth International Conference on Rapidly Quenched Metals, Wurzburg, Germany, ed. by Steeb, S. and Warlimont, H. (North Holland, Amsterdam, 1985), p. 895.Google Scholar
[7] Appleton, B. R., Holland, O. W., Poker, D. B., Narayan, J. and Fathy, D., Nucl. Inst. and Methods in Phys. Research B7 (1985) 639.Google Scholar
[8] Taylor, A., Allen, C. W. and Ryan, E. A., Nucl. Inst. and Methods in Phys. Res. B24 (1987) 598.Google Scholar
[9] B.Kestel, to be published.Google Scholar
[10] Birtcher, R.C. and Jäger, W., Ultramicroscopy 22 (1987) 267.Google Scholar
[11] Hastings, I. J. and Stoute, R.L., J. Nucl. Mater 37 (1970) 295.Google Scholar
[12] Birtcher, R. C., Allen, C. W., Rehn, L. E. and Hofman, G. L., J. Nucl. Mater., to be published.Google Scholar