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织构对锆合金内压蠕变性能的影响 被引量：2

Effects of Texture on Inner Pressure Creep Behaviors of Advanced Zirconium Alloys
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摘要 研究了两种组织形貌相似的锆合金M5TM和N36锆合金核燃料包壳管材的内压蠕变性能,利用X射线衍射仪分析了它们的织构,根据试验数据分析了试验应力水平对蠕变机理的影响,提出用合金在试验条件下的屈服应力作为规一化值建立蠕变速率-规一化应力关系曲线,该法更能够体现合金织构对内压蠕变行为的影响,尤其是蠕变幂函数规律失效的临界转变应力水平。 The inner pressure creep behaviors of advanced Zr alloy M5TM and N36 with similar microstructure have been measured,and their textures have been observed by XRD.The effects of testing stress on creep mechanism have been approached based on experimental data.The equation of creep rate via normalization stress has been established by taking the yield stress of the alloys as normalization values in the testing conditions,which can fully respond the effects of texture on the inner pressure creep behavior in the condition of the abort of creep power function.
作者 彭继华 李文芳 Bechade Jean-Luc Rauchy Morry
机构地区 华南理工大学机械工程学院 SMRA/EEN/CEA/Saclay
出处 《特种铸造及有色合金》 CAS CSCD 北大核心 2007年第7期499-502,共4页 Special Casting & Nonferrous Alloys
关键词 锆合金 织构 内压蠕变 Zr Alloy,Texture,Inner Pressure Creep
分类号 TG146.414 [金属学及工艺—金属材料] TG115.22 [金属学及工艺—物理冶金]
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参考文献17

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二级参考文献14

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共引文献18

同被引文献18

  • 1CUI WenFang1,GUO AiHong2,ZHOU Lian3 & LIU ChunMing1 1 Key Laboratory for Anisotropy and Texture of Materials (Ministry of Education),Northeastern University,Shenyang 110004,China,2 Luoyang Ship Material Research Institute,Luoyang 471039,China,3 Northwest Institute of Nonferrous Metals Research,Xi’an 710016,China.Crystal orientation dependence of Young's modulus in Ti-Nb-based β-titanium alloy[J].Science China(Technological Sciences),2010,53(6):1513-1519. 被引量：6
  • 2刘文庆,李强,周邦新,严青松,姚美意.热处理制度对N18新锆合金耐腐蚀性能的影响[J].核动力工程,2005,26(3):249-253. 被引量：19
  • 3彭继华,李文芳,Jean-Luc Bechade,Rauchy Morry.织构对锆合金拉伸和爆破性能的影响[J].材料研究与应用,2007,1(2):122-126. 被引量：10
  • 4Peng J, Bechade Jean-Luc, Maury R, Guilbert Th, Toumier I. Mechanical properties of cladding tubes obtained from Framatome- ANP and from NPIC [R]. Saclay/CEA/Paris: SRMA/DEN/CEA, 2002.
  • 5Mardon J P, Charquet D, Senevat J. Influence of composition and fabrication process on out-of-pile and in-pile properties M5 alloy [A]. Sabol G P, Moan G D. Zirconium in the Nuclear Industry (ASTM STP 1354) [C]. New York: Mc-Hill, 2000. 505.
  • 6Seibold A, Matron J P. M5TM cladding experience in European PWRs [J]. Jahrestagung kerntechnik, 2002, 35: 293.
  • 7Gilbon D, Soniak A, Doriot S. Irradiation creep and growth behavior and microstruetural evolution of advanced Zr-based alloys [A]. Sabol G P, Moan G D. Zirconium in the Nuclear Industry (ASTM STP 1354) [C]. New York: Mc-Hill, 2000. 51.
  • 8Zhao W J, Zhou B X. Studies of new zirconium alloys [ J ]. Rare Metal Materials and Engineering, 2001, 30: 19.
  • 9Murty K L, Wiratmo J R. Transition in creep mechanisms and creep anisotropy in Zr-1 Nb-1Sn-0.2Fe sheet [J]. Nud. Eng. Des., 1995, 156: 359.
  • 10Sabol G P, Kilp G R, Balfour M G. Development of a cladding alloy for high burnup [A]. Van Swam L F P, Eueken C M. Zirconium in the Nuclear Industry (ASTM STP 1023) [C]. New York: Mc-Hill, 1989. 227.

引证文献2

二级引证文献23

特种铸造及有色合金
2007年 第7期

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