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Irradiation-Induced Reduction of Microcracking in Zirconolite

Published online by Cambridge University Press:  26 February 2011

F. W. Clinard Jr ,
D. S. Tucker ,
G. F. Hurley ,
C. D. Kise  and
J. Rankin
F. W. Clinard Jr
Affiliation:
Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM 81544
D. S. Tucker
Affiliation:
Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM 81544
G. F. Hurley
Affiliation:
Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM 81544
C. D. Kise
Affiliation:
Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM 81544
J. Rankin
Affiliation:
Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM 81544
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Abstract

238Pu-substituted zirconolite (CaPuTi 2O7 ) was stored near ambient temnerature for 231 days, equivalent to an aipha decay dose of 3.1×1025 α/m3 or 3×105 years of storage time for SYNROC ceramic nuclear waste. Periodic indentation testing showed that hardness was decreased by alpha decay-induced conversion to the metamict state, while fracture toughness and resistance to cracking were increased, apparently as a consequence of the formation of a heterogeneous microstructure. These results imply improved stability of this nuclear waste phase as a result of self-irradiation damage.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 44: Symposium N – Scientific Basis for Nuclear Waste Management VIII , 1984 , 663
Copyright
Copyright © Materials Research Society 1985

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