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Metallographic Analysis of Irradiated RERTR-3 Fuel Test Specimens.

DE2001768609

Publication Date	2001
Personal Author	Meyer, M. K.; Hofman, G. L.; Strain, R. V.; Clark, C. R.; Stuart, J. R.
Page Count	14
Abstract	The RERTR-3 irradiation test was designed to investigate the irradiation behavior of aluminum matrix U-MO alloy dispersion fuels under high-temperature, high-fission-rate conditions. Initial postirradiation examination of RERTR-3 fuel specimens has concentrated on binary U-MO atomized fuels. The rate of matrix aluminum depletion was found to be higher than predictions based on low temperature irradiation data. Wavelength Dispersive X-ray Spectroscopy (WDS) indicates that aluminum is present in the interior of the fuel particles. WDS data is supported by a mass and volume balance calculation performed on the basis of image analysis results. The depletion of matrix aluminum seems to have no detrimental effects on fuel performance under the conditions tested to date.
Keywords	Irradiation Fuel tests Research and test reactors Metallurgic effects Aluminum alloys Fission products Burnup Temperature effects Molybdenum alloys Nuclear reactions Dispersion nuclear fuels Fuel elements Matrix materials Radiation effects Performance
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200122
Contract Number	DE-W-31-109-ENG-38

Metallographic Analysis of Irradiated RERTR-3 Fuel Test Specimens.

Metallographic Analysis of Irradiated RERTR-3 Fuel Test Specimens.
DE2001768609

Publication Date	2001
Personal Author	Meyer, M. K.; Hofman, G. L.; Strain, R. V.; Clark, C. R.; Stuart, J. R.
Page Count	14
Abstract	The RERTR-3 irradiation test was designed to investigate the irradiation behavior of aluminum matrix U-MO alloy dispersion fuels under high-temperature, high-fission-rate conditions. Initial postirradiation examination of RERTR-3 fuel specimens has concentrated on binary U-MO atomized fuels. The rate of matrix aluminum depletion was found to be higher than predictions based on low temperature irradiation data. Wavelength Dispersive X-ray Spectroscopy (WDS) indicates that aluminum is present in the interior of the fuel particles. WDS data is supported by a mass and volume balance calculation performed on the basis of image analysis results. The depletion of matrix aluminum seems to have no detrimental effects on fuel performance under the conditions tested to date.
Keywords	Irradiation Fuel tests Research and test reactors Metallurgic effects Aluminum alloys Fission products Burnup Temperature effects Molybdenum alloys Nuclear reactions Dispersion nuclear fuels Fuel elements Matrix materials Radiation effects Performance
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200122
Contract Number	DE-W-31-109-ENG-38