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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

1. Daniel, J. L., Mellinger, G. B., and Barner, J. O., “Reference and Testing Materials Available from the Materials Characterization Center,” in Scientific Bases for Nuclear Waste Management VIIL edited by Jantzen, C. M., Stone, J. A., and Ewing, R. C. (Mater. Res. Soc. Proc. 44 Pittsburg, PA 1985) p. 723–728.Google Scholar
2. Barner, J. O., “Characterization of LWR Spent Fuel MCC-Approved Testing Material-ATM-101,” PNL-5109, Rev. 1, Pacific Northwest Laboratory, Richland, Washington (1985).Google Scholar
3. Guenther, R. J., Blahnik, D. E., Campbell, T. K., Jenquin, U. P., Mendel, J. E., Thomas, L. E., and Thornhill, C. K., “Characterization of Spent Fuel Approved Testing Material--ATM-103,” PNL-5109–103, Pacific Northwest Laboratory, Richland, Washington (1988).Google Scholar
4. Guenther, R. J., Blahnik, D. E., Campbell, T. K., Jenquin, U. P., Mendel, J. E., and Thornhill, C. K., “Characterization of Spent Fuel Approved Testing Material--ATM-106,” PNL-5109–106, Pacific Northwest Laboratory, Richland, Washington (1988).CrossRefGoogle Scholar
5. Croff, A. G.. “Revised Uranium-Plutonium Cycle PWR and BWR Models for the ORIGEN Computer Code,” ORNL/TM-6051, Oak Ridge National Laboratory, Oak Ridge, Tennessee (1978).CrossRefGoogle Scholar
6. Croff, A. G.. “A User's Manual for the 0RIGEN2 Computer Code,” ORNL/TM-7175, Oak Ridge National Laboratory, Oak Ridge, Tennessee (1978).Google Scholar
7. Roddy, J. W. and Mailen, J. C., “Radiological Characteristics of Light-Water Reactor Spent Fuel: A Literature Survey of Experimental Data,” ORNL/TM-10105, Oak Ridge National Laboratory, Oak Ridge, Tennessee (1987).Google Scholar