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作 者:高巍[1] 徐悠[1] 王正品[1] 杨文涛[1] 石崇哲[1]
机构地区:[1]西安工业大学材料与化工学院,西安710021
出 处:《西安工业大学学报》2013年第12期993-999,共7页Journal of Xi’an Technological University
基 金:陕西省自然基金项目(2011JM7006)
摘 要:为探讨不同淬火温度对核燃料包壳管Zr-4合金力学性能的影响.本文分析了Zr-4合金的显微组织,通过对再结晶退火态的Zr-4合金进行不同温度淬火及回火热处理,在不同热处理状态下对试样进行室温环向拉伸试验,分析对比了试样的拉伸力学性能,并对拉伸后的试样进行断口扫描,分析断裂机理.试验结果表明:包壳管Zr-4合金在980℃淬火后晶粒弦长为145.62μm,相比920℃、950℃的弦长增大,其抗拉强度为740MPa,屈服强度为649MPa.淬火后断口类型属解理脆性断裂.The microstruetures and properties of Zr-4 alloy after heat-treatment in different quenching temperatures were studied. The tensile properties of tubes of different heat-treatment were studied by means of static tensile test at room temperature. The fracture mechanisms of Zr-4 tubes after tensile test were studied by SEM. The result showed that the grain chord length after 980 ~C quenching was 145.62 μm and was longer than that at other temperatures. The tensile strength was 740 MPa, and the yield strength was 649 MPa after quenching at 980 ℃. The tensile fracture of Zr-4 alloys occured in the manner of cleavage brittle fracture at room temperature according to the SEM fracture surface observation.
分 类 号:TG156.3[金属学及工艺—热处理]
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