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Mechanical anisotropy and construction of flow stress diagrams during the annealing of Zr-1% Sn alloy

机译:Zr-1%Sn合金退火过程中的力学各向异性和流变应力图的构建

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In the present study the annealing behavior of 60% reduced and stress relieved Zircaloy-4 nuclear fuel cladding tube is studied over a temperature range of 300-1000 ℃ and an annealing time range of 10~3 to 10~5 s. The annealing effects were monitored using Knoop microhardness measurements and flow stress diagrams were developed to study the mechanical anisotropy evolution in the tubing. The determined values of the mechanical anisotropy ratios show that the tubing undergoes a significant mechanical anisotropy evolution during annealing.
机译:在本研究中,研究了在300-1000℃的温度范围和10〜3至10〜5 s的退火时间范围内,Zircaloy-4核燃料包壳管减少了60%的应力并消除了应力的退火行为。使用努氏显微硬度测量监测退火效果,并建立流动应力图以研究管道中的机械各向异性演变。机械各向异性比的确定值表明,在退火过程中,油管经历了明显的机械各向异性演变。

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