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Effect of Storage Temperature on Self-Irradiation Damage of 238PU-Substituted Zirconolite*

Published online by Cambridge University Press:  21 February 2011

F. W. Clinard Jr. ,
D. E. Peterson ,
D. L. Rohr ,
R. B. Roof  and
L. W. Hobbs
F. W. Clinard Jr.
Affiliation:
University of California, Los Alamos National Laboratory, Los Alamos, NM 87545
D. E. Peterson
Affiliation:
University of California, Los Alamos National Laboratory, Los Alamos, NM 87545
D. L. Rohr
Affiliation:
University of California, Los Alamos National Laboratory, Los Alamos, NM 87545
R. B. Roof
Affiliation:
University of California, Los Alamos National Laboratory, Los Alamos, NM 87545
L. W. Hobbs
Affiliation:
Department of Materials Science and Engineering, Massachusetts Institute of Technology, Cambridge, MA 02139
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Abstract

238Pu-substituted cubic zirconolite (CaPuTi2 O7) was stored at ambient temperature, 575 K and 875 K until alpha decay doses of 2.4 to 3.6 × 1025/m3 had been accumulated. The ambient temperature material swelled to a saturation value of 5.5 vol%, and the originally crystalline structure was transformed to one with an amorphous matrix and small domains that had retained their crystallinity. At 575 K lesser amounts of swelling (4.1 vol%) and transformation were observed, reflecting concurrent partial recovery. The material held at 875 K remained crystalline, swelled only 0.4 vol%, and exhibited formation of isolated defect clusters.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 15: Symposium D – Scientific Basis for Nuclear Waste Management VI , 1982 , 437
Copyright
Copyright © Materials Research Society 1983

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Footnotes

*

Work performed under the auspices of the U. S. Department of Energy.

References

REFERENCES

1. Ringwood, A. E., Kesson, S. E., Ware, N. G., Hibberson, W. O. and Major, A., Geochem. J. 13, 141 (1979).CrossRefGoogle Scholar
2. Dosch, R. G., Lynch, A. W., Headley, T. J. and Hlava, P. F. in: Scientific Basis for Nuclear Waste Management Vol. 3, Moore, J. G., ed. (Plenum Press, New York 1981) pp. 123–130.Google Scholar
3. Clinard, F. W. Jr., Hobbs, L. W., Land, C. C., Peterson, D. E., Rohr, D. L. and Roof, R. B., J. Nucl. Mater. 105, 248 (1982).CrossRefGoogle Scholar
4. Clinard, F. W. Jr., Land, C. C., Peterson, D. E., Rohr, D. L., and Roof, R. B., in: Scientific Basis for Nuclear Waste Management, Vol. 6, Topp, S. V., ed. (North-Holland, New York 1982) pp. 405–412.Google Scholar
5. Hobbs, L. W. in: Analytical Microscopy, Hren, J. J., Goldstein, J. I. and Joy, D. C., eds. (Plenum, New York 1980) pp. 437–480.Google Scholar
6. Reeve, K. D. and Woolfrey, J. L., J. Aust. Ceram. Soc., 16, 10 (1980).Google Scholar
7. Gray, W. J., Wald, J. W., and Turcotte, R. P., “Radiation Damage Studies Related to Nuclear Waste Forms”, Report PNL-4145 (1981).Google Scholar
8. Headley, T. J., Arnold, G. W., and Northrup, C. J. M. in: Scientific Basis for Nuclear Waste Management Vol. 5, Lutze, W., ed. (North-Holland, New York) in press.Google Scholar
9. Ewing, R. C., Haaker, R. F., Headley, T. J., and Hlava, P. F., op. cit. ref. 4, pp. 249–256.Google Scholar
10. Sinclair, W. and Ringwood, A. E., Geochem. J. 15, 229 (1981).Google Scholar
11. Pudovkina, Z. V. and Pyatenko, Yu. A., Akad. Nauk SSSR Mineral. Muzei Tr. 17, 124 (1966).Google Scholar
12. Howard, C. J. and Sabine, T. M., J. Phys. C: Solid State Phys. 7, 3453 (1974).Google Scholar
13. This work, an interim report of which was given in ref. 4, has been carried to completion (to be published).Google Scholar
14. Price, R. J., J. Nucl. Mater. 33, 17 (1969).Google Scholar