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:
-
10%
-
20%
-
30%
-
40%
-
50%