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Detailed Characterization of LWR Fuel Rods for the U.S. Civilian Radioactive Waste Management Program

Published online by Cambridge University Press:  26 February 2011

Richard J. Guenther ,
D. E. Blahnik ,
T. K. Campbell ,
U. P. Jenquin ,
J. E. Mendel  and
C. K. Thornhill
Richard J. Guenther
Affiliation:
Pacific Northwest Laboratory, P. 0. Box 999, Richland, WA 99352
D. E. Blahnik
Affiliation:
Pacific Northwest Laboratory, P. 0. Box 999, Richland, WA 99352
T. K. Campbell
Affiliation:
Pacific Northwest Laboratory, P. 0. Box 999, Richland, WA 99352
U. P. Jenquin
Affiliation:
Pacific Northwest Laboratory, P. 0. Box 999, Richland, WA 99352
J. E. Mendel
Affiliation:
Pacific Northwest Laboratory, P. 0. Box 999, Richland, WA 99352
C. K. Thornhill
Affiliation:
Pacific Northwest Laboratory, P. 0. Box 999, Richland, WA 99352
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Abstract

Characterizations are being conducted on light-water reactor (LWR) spent fuel with peak burnups from ∼31 to 46 MWd/kgM and rod-average fission gas releases of ∼0.3 to 11%. Measured concentrations of nuclides agreed within ∼10 to 15% of the predicted amounts. Radiochemistry of deposits on the cladding interior surface, fuel ceramography, beta/gamma autoradiog-raphy, and gamma scan data were consistent with fuel burnups and apparent operating temperatures. Microstructural observations also indicated increased porosity at the fuel center in high-release fuels and at the edge in high-burnup fuels. Cladding oxide thickness increased with exterior cladding temperatures as did the trend in hydriding.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 127: Symposium BERLIN – Scientific Basis for Nuclear Waste Management XII , 1988 , 325
Copyright
Copyright © Materials Research Society 1989

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References

REFERENCES

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