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织构对先进锆合金蠕变性能各向异性的影响 被引量:16

Effect of Texture on Anisotropy of Creep Behavior of Advanced Zirconium Alloys
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摘要 研究了两种组织形貌相似的先进锆合金M5TM和N36锆合金核燃料包壳管材的单轴拉伸和内压蠕变性能。利用X射线衍射仪分析了它们的织构。试验发现两种先进锆合金包壳材料的蠕变性能表现出明显的各向异性。根据试验条件下的蠕变机理,结合弹性粘塑性自洽模型定性地分析了织构对锆合金管材蠕变各向异性的影响,解释了先进锆合金各向异性随应力指数变化的共性规律。揭示了织构与先进锆合金管材蠕变各向异性的定性关系。由于成分和织构因素的共同作用,在研究的试验条件下,N36合金的初始蠕变应变、稳态蠕变速率低于M5合金。织构是合金蠕变行为产生各向异性的主要原因,对于再结晶状态的先进锆合金包壳管,具有(0002)织构特征时,应力指数越高(即施加的应力水平越高),其蠕变的各向异性值越大。 The axial tension creep behavior and inner pressure creep behavior of advanced zirconium alloys,M5 and N36,were investigated.Their texture was studied by means of X-ray diffraction.Anisotropy of creep behavior of two zirconium clad tubes was studied.To explain the rule of creep anisotropy in zirconium clad tubes,the qualitative dependence of the creep anisotropy with texture was established by jointing creep mechanism with elastic-viscous-plastic self consistent model under the experiment condition.
出处 《稀有金属》 EI CAS CSCD 北大核心 2008年第1期1-6,共6页 Chinese Journal of Rare Metals
关键词 先进锆合金 织构 蠕变 各向异性 advanced zirconium alloys texture creep anisotropy
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参考文献15

  • 1Peng 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.
  • 2Mardon 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.
  • 3Seibold A, Matron J P. M5TM cladding experience in European PWRs [J]. Jahrestagung kerntechnik, 2002, 35: 293.
  • 4Gilbon 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.
  • 5Zhao W J, Zhou B X. Studies of new zirconium alloys [ J ]. Rare Metal Materials and Engineering, 2001, 30: 19.
  • 6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
  • 7Murty 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.
  • 8Sabol 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.
  • 9Nikulina A V, Markelov V A, Peregud M M. Zirconium alloy E635 as a material for fuel rod cladding and other components of VVER and RBMK cores [A]. Bradley E R, Sabol G P. Zirconium in the Nuclear Industry (ASTM STP 1295) [C]. New York: Mac-Hill, 1996. 785.
  • 10Nikulina A V, Goncharov V I, Markelov V A. Effects of microsture on ductility and fracture resistance of Zr-1.2Sn-1 Nb- 0.4Fe alloy [A]. Bradley E R, Sabol G P. Zirconium in the Nu-clear Industry (ASTM STP 1295) [C]. New York: Mac-Hill, 1996. 695.

二级参考文献43

  • 1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
  • 2[1]PENG J,BECHADE J L,MAURY R,et al.Mechanical properties of cladding tubes obtained from Framatome-ANP and from NPIC[R].Paris:SRMA/DEN/CEA/Saclay,2002.
  • 3[2]MARDON J P,CHARQUET D,SENEVAT J.Influence of composition and fabrication process on out-of-pile and in-pile properties M5 alloy[C]//SABOL G P,MOAN G D.Zirconium in the nuclear industry(ASTM STP 1354).New York:Mc-Hill,2000:505-524.
  • 4[3]SEIBOLD A,MARTON J P.M5 cladding experience in European PWRs[C].Stuttgart:Jahrestagung Kerntech nik,2002:293-298.
  • 5[4]GILBON D,SONIAK A,DORIOT S,et al.Irradiation creep and growth behavior and microstructural evolution of advanced Zr-based alloys[J].Zirconium in the Nuclear Industry,2000,1354:51-73.
  • 6[5]ZHAO W J,ZHOU B X.Studies of new zirconium alloys[J].Rare Metal Materials and Engineering,2001,30:19-23.
  • 7[7]MURTY K L,WIRATMO,J R.Transition in creep mechanisms and creep anisotropy in Zr-1Nb-1Sn-0.2Fe sheet[J].Nucl Eng Des,1995,156:359-371.
  • 8[8]SABOL G P,KILP G R,BALFOUR M G,et al.Development of a cladding alloy for high burnup[J].Zirconium in the Nuclear Industry,1989.1023:227-244.
  • 9[9]NIKULINA A V,MARKELOV V A,PEREGUD M M,et al.Zirconium alloy E635 as a material for fuel rod cladding and other components of VVER and RBMK cores[J].Zirconium in the Nuclear Industry,1996,1295:785-804.
  • 10[10]NIKULINA A V,GONCHAROV V I,MARKELOV V A,et al.Effects of microsture on ductility and fracture resistance of Zr-1.2Sn-1Nb-0.4Fe alloy[J].Zirconium in the Nuclear Industry,1996,1295:695-709.

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