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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

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