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Fission gas release (FGR) and volumetric swelling data for various U-Zr alloys ir radiated at approximately 600℃.
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In order to study the thermal deformation behavior of uranium-50wt.%zirconium, used Gleeble 3800 thermal simulation testing machine to carry out compression deformation experiments at different temperatures for this material. The effects of deformation temperature and strain rate on the alloy were studied. The results show that the peak stress of U...
Context in source publication
Context 1
... study found that compared to other U-Zr alloy systems, the δ-UZr2 structure exhibits very small volume expansion and fission gas release. The quantitative results of this study are shown in Table 1 below, with the last row of data (sample Zr1) corresponding to the δ-UZr2 phase sample -e.g., [3]. The degree of fission gas release and volume expansion in δ-UZr2 samples is significantly lower than that exhibited by other U-Zr compositions. ...Similar publications
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