2019
DOI: 10.1007/s40195-019-00964-6
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Texture Evolution and Dynamic Recrystallization of Zr–1Sn–0.3Nb–0.3Fe–0.1Cr Alloy During Hot Rolling

Abstract: In the present work, the sheets of Zr-1Sn-0.3Nb-0.3Fe-0.1Cr alloy were hot rolled with different reductions (10%, 30%, 50%, and 60%) at 1023 K and 1073 K. The microstructure evolutions including grain microstructure, texture, and dislocation were investigated, using electron backscattering diffraction and transmission electron microscope. The results showed that dislocation slip, twinning, and dynamic recrystallization (DRX) were the main deformation mechanisms. DRX was found to be promoted by larger reduction… Show more

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Cited by 6 publications
(2 citation statements)
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“…Compared to the original microstructure [15], the average grain size of the alloy decreased from 3.48 µm to about 0.24 µm after ECAP. According to the average misorientation angle of grains, the grains of this alloy can be divided into three types [32]: (i) average angle < 1 • , recrystallized grains (represented in blue); (ii) 1 • < average angle < 7.5 • , substructure grains (marked in yellow); (iii) average angle > 7.5 • , deformed grains (indicated in red). The recrystallization map characterized in Figure 2b shows that the microstructure of the UFG TiFeB alloy consists of deformed grains (~63%), substructure grains (~34.3%) and recrystallized grains (only ~2.7%).…”
Section: Initial Microstructurementioning
confidence: 99%
“…Compared to the original microstructure [15], the average grain size of the alloy decreased from 3.48 µm to about 0.24 µm after ECAP. According to the average misorientation angle of grains, the grains of this alloy can be divided into three types [32]: (i) average angle < 1 • , recrystallized grains (represented in blue); (ii) 1 • < average angle < 7.5 • , substructure grains (marked in yellow); (iii) average angle > 7.5 • , deformed grains (indicated in red). The recrystallization map characterized in Figure 2b shows that the microstructure of the UFG TiFeB alloy consists of deformed grains (~63%), substructure grains (~34.3%) and recrystallized grains (only ~2.7%).…”
Section: Initial Microstructurementioning
confidence: 99%
“…Zirconium alloy has become the preferred material for positioning grids in nuclear reactors because of its good nuclear properties, low thermal neutron absorption crosssection, high tensile strength, good corrosion resistance and comprehensive mechanical properties [1][2][3][4][5][6]. A positioning grid is a key clamping structure for fixing the transverse and axial positions of fuel assemblies in nuclear reactors [7][8][9][10][11]. In recent years, transverse stamping using a multi-station progressive die has generally been used as the main method for the preparation of positioning grids with zirconium alloy [12][13][14][15][16].…”
Section: Introductionmentioning
confidence: 99%