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退火态及马氏体态M5锆合金管轴向拉伸性能研究 被引量:1

Study on Axial Tensile Properties of Annealed and Martensitic M5 Zirconium Alloy Tubes
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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。 Abstract: 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.
出处 《钛工业进展》 北大核心 2015年第5期23-26,共4页 Titanium Industry Progress
关键词 M5锆合金 轴向拉伸 马氏体 M5 zirconium alloy axial tensile martensite
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  • 1赵文金,周邦新,苗志,彭倩,蒋有荣,蒋宏曼,庞华.我国高性能锆合金的发展[J].原子能科学技术,2005,39(B07):2-9. 被引量:95
  • 2梁志德.现代织构分析的进展[J].金属学报,1997,33(2):133-142. 被引量:5
  • 3扎依莫夫斯基AC.核动力用锆合金[M].北京:原子能出版社,1988.241~243.Zhayimofergy AC. Zirconium Alloys for Atomic Energy Power[M].Beijing: Atomic Energy Press, 1988.241~243(in Chinese).
  • 4丘利,胡玉和.X射线衍射技术及设备[M].北京:冶金工业出版社,2001:121-154
  • 5弗罗斯特BRT.核材料:第II部分[M].周邦新,译.北京:科学出版社,1999.
  • 6Tenckhoff E. Operable Deformation systems and mechanical behavior of textured zircaloy tubing: Zirconium in Nuclear Industry, ASTM STP 551 [ C ]. Philadelphia : American Society for Testing and Materials , 1974.
  • 7Daniel R C. In-pile dimensional changes of zircaloy4 tubing having low hoop stresses [ J]. Nuclear Technology, 1972, 14: 171.
  • 8Charit I, Murty K L. Texture and creep anisotropy in zirconium alloys[J]. Materials Science Forum, 2007, 539 - 543 : 3377 - 3382.
  • 9Cox B. Environmentally-induced cracking of zirconium alloys--A review[ J ]. Journal of Nuclear Materials, 1990, 170(1) : 1 -23.
  • 10Causey A R, Woo C H, Holt R A. The effect of intergranular stresses on the texture dependence of irradiation growth in zirconium alloys [ J ]. Journal of Nuclear Materials, 1988, 159 : 225.

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