退火态及马氏体态M5锆合金管轴向拉伸性能研究
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摘要
M5锆合金经β相区淬火后会发生马氏体相变,为了解具有马氏体相的M5锆合金管的轴向拉伸性能并研究马氏体相对锆合金管轴向拉伸性能的影响,通过静态拉伸试验对退火态及马氏体态的M5锆合金包壳管室温轴向拉伸性能进行了研究,并采用扫描电镜对静态拉伸断口进行了观察。结果表明,马氏体态M5锆合金管比退火态M5锆合金管强度高,但塑性和韧性低;从微观断口形貌来看,两种状态的M5锆合金管轴向拉伸断口形貌均为韧窝,断裂机理均为微孔聚集型断裂,断裂类型均为韧性断裂。
M5 zirconium alloys change into martensite after quenching in β phase zone. To understand the M5 zirconium alloy tubes with martensite and find out the influence of martensite on axial tensile properties of M5 zirconium alloy tubes,the tensile properties of annealed and martensitic M5 zirconium alloy nuclear fuel cladding tubes were studied by static axial tensile test at room temperature. Fracture morphology was analyzed by scanning electron microscope( SEM).The results show that martensitic M5 zirconium alloy tubes have higher strength but lower ductility and toughness than annealed M5 zirconium alloy tubes. The fracture morphology of martensitic and annealed M5 zirconium alloy tubes are ductile fracture with dimples,the fracture occurs in the manner of microvoid coalescence according to SEM observation.
M5 zirconium alloys change into martensite after quenching in β phase zone. To understand the M5 zirconium alloy tubes with martensite and find out the influence of martensite on axial tensile properties of M5 zirconium alloy tubes,the tensile properties of annealed and martensitic M5 zirconium alloy nuclear fuel cladding tubes were studied by static axial tensile test at room temperature. Fracture morphology was analyzed by scanning electron microscope( SEM).The results show that martensitic M5 zirconium alloy tubes have higher strength but lower ductility and toughness than annealed M5 zirconium alloy tubes. The fracture morphology of martensitic and annealed M5 zirconium alloy tubes are ductile fracture with dimples,the fracture occurs in the manner of microvoid coalescence according to SEM observation.
引文
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[2]Mardon P,Charquet D,Senevat J,et al.Update on the development of advancement zirconium alloys for PWR fuel rod claddings[M].Portland:ANS,1991:405.
[3]袁改焕,卫新民.锆合金研究进展及我国核电站用锆材国产化的思考[J].钛工业进展,2011,28(6):18-22.
[4]张长义,宁广胜,佟振峰,等.M5锆合金轴向和环向拉伸性能测试[J].原子能科学技术,2005,39(增刊1):34-36.
[5]金尧,戴振羽,高庆.Zr-4合金管环向性能测试研究[J].核动力工程,1994,15(1):84-87.
[6]刘建章.核材料科学与工程[M].北京:化学工业出版社,2007:77.