Metallographic Analysis of Irradiated RERTR-3 Fuel Test Specimens.

Meyer, M. K. ; Hofman, G. L. ; Strain, R. V. ; Clark, C. R. ; Stuart, J. R.

Technical Information Center Oak Ridge Tennessee

关键词: Irradiation;    Fuel tests;    Research and test reactors;    Metallurgic effects;    Aluminum alloys;   

RP-ID  :  DE2001768609

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

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.