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

  • Richard J. Guenther (a1), D. E. Blahnik (a1), T. K. Campbell (a1), U. P. Jenquin (a1), J. E. Mendel (a1) and C. K. Thornhill (a1)...

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.

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

  • Richard J. Guenther (a1), D. E. Blahnik (a1), T. K. Campbell (a1), U. P. Jenquin (a1), J. E. Mendel (a1) and C. K. Thornhill (a1)...

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