欢迎登录材料期刊网

材料期刊网

高级检索

锆合金被广泛应用于核反应堆中,作为燃料元件的包壳材料或堆内结构部件,织构会影响其众多的应用性能,因此织构的研究及控制在锆合金的开发利用中具有重要作用.综述了锆合金塑性变形的滑移和孪生系统;锆合金管板材的织构特点及控制方法;热轧温度对锆合金板材织构的影响以及退火处理锆合金织构的演化;并分别总结了织构与锆合金屈服强度、蠕变强度、碘致应力腐蚀开裂、氢化物取向分布以及辐照生长等性能的相互关系.

参考文献

[1] 赵文金,苗志,蒋宏曼,于晓卫,李卫军,李聪,周邦新.Zr-Sn-Nb合金的腐蚀行为研究[J].中国腐蚀与防护学报,2002(02):124-128.
[2] 弗罗斯特 B R T;周邦新.核材料[M].北京:科学出版社,1999
[3] Tenckhoff E .Deformation Mechanisms,Texture,and Anisotropy in Zirconium and Zircaloy[R].ASTM-STP 966,1988.
[4] 王卫国;周邦新 .锆合金板织构的控制[J].核动力工程,1994,15(02):158.
[5] Pochettino A A;Gannio N;Edwards C et al.Texture and pyramidal slip in Ti,Zr and their alloys[J].Scripta Metallurgica et Materialia,1992,27:1859.
[6] Rapperport E J;Hartley C S .Deformation Modes of Zirconium at 77,300,575 and 1075 K[R].NMI-1221,Nuclear Metals,Inc.Concord,MA,1959.
[7] Chun YB.;Kim MH.;Kwun SI.;Chae SW.;Hwang SK. .Effect of Mo addition on the crystal texture and deformation twin formation in Zr-based alloys[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2001(1):31-41.
[8] 王卫国;周邦新 .轧制温度对Zr-4合金板织构的影响[J].核动力工程,1996,17(03):255.
[9] Francillette H;Bacroix B;Gasperini M .Effect of initial texture on deformation mechanisms and texture evolutions of Zr α polycrystals deformed by channel-die compression tests[J].Materials Science and Engineering A,1997,234-236:974.
[10] 彭倩,赵文金,刘彦章,孙长龙.Zr-4合金板α相高温区轧制的织构演化[J].核动力工程,2003(02):133-136.
[11] A. SALINAS-RODRIGUEZ .GRAIN SIZE EFFECTS ON THE TEXTURE EVOLUTION OF α-Zr[J].Acta Metallurgica et Materialia,1995(2):485-498.
[12] 扎依莫夫斯基 A C;姚敏智.核动力用锆合金[M].北京:原子能出版社,1988
[13] Cook C S;Sabol G P;Sekera K R.Texture control in zircaloy tubing through processing[A].Philadelphia:American Society for Testing and Materials,1991:80.
[14] Rittenhouse P L;Picklesimer M L .The Effects of Fabrication Variables on the Preferred Orientation and Anisotropy of Strain Behavior[R].ORNL-2948,1961.
[15] Linga M K;Sheikh M T.Deformation and recrystallization texture and anisotropic plastic properties of zircaloy sheet[J].SMiRT 11 Transactions,1991:61.
[16] Tenckhoff E;Rittenhouse P L .Annealing texture in zircaloy tubing[J].Journal of Nuclear Materials,1970,35:14.
[17] Keeler J H;Geisler A H .Preferred orientation in beta-annealed zirconium[J].Journal of Metals Transactions AIME,1955,202:395.
[18] Kearns J J .Thermal Expansion and Preferred Orientation in Zircaloy[R].WAPD-TM-472,UC-25:Metals,Ceramics,and Materials,TID-4500,1965.
[19] Christodoulou N;Turner P A;Ho E T C et al.Anisotropy of yielding in a Zr-2.5Nb pressure tube material[J].Metallurgical and Materials Transactions A:Physical Metallurgy and Materials Science,2000,31:409.
[20] Fregonese M;Regnard C;Rouillon L.Failure mechanisms of irradiated Zr alloys related to PCI:Activated slip systems,localized strains and iodine induced stress corrosion cracking[A].West Conschohocken,PA:American Society for Testing and Materials,2000:377.
[21] Causey A R;Elder J E;Holt R A.On the anisotropy of in-reactor creep of Zr-2.5Nb tubes[A].Philadelphia:American Society for Testing and Materials,1994:202.
[22] Knorr D B;Pelloux R M .Effects of texture and microstructure on the propagation of iodine stress corrosion cracking in zircaloy[J].Metallurgical and Materials Transactions A:Physical Metallurgy and Materials Science,1982,13:73.
[23] Cox B .Pellet-clad interaction (PCI) failures of zirconium alloy fuel cladding-A review[J].Journal of Nuclear Materials,1990,172:249.
[24] Cox B .Environmentally-induced cracking of zirconium alloys-A review[J].Journal of Nuclear Materials,1990,170:1.
[25] Arunachalam V S;(O)stberg G;Lehtinen B .Remarks on the habit planes of zirconium hydride in zircaloy-2[J].Journal of Nuclear Materials,1968,28:336.
[26] Sung Soo Kim;Sang Chul Kwon;Young Suk Kim .The effect of texture variation on delayed hydride cracking behavior of Zr-2.5%Nb plate[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,1999(1):52-59.
[27] Causey 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.
[28] Holt R A .Microstructure dependence of irradiation creep and growth of zirconium alloys[J].Journal of Nuclear Materials,1980,90:193.
[29] Daniel R C .In-pile dimensional changes of zircaloy-4 tubing having low hoop stresses[J].Nuclear Technology,1972,14:171.
上一张 下一张
上一张 下一张
计量
  • 下载量()
  • 访问量()
文章评分
  • 您的评分:
  • 1
    0%
  • 2
    0%
  • 3
    0%
  • 4
    0%
  • 5
    0%