期刊文献+
任意字段
题名或关键词
题名
关键词
文摘
作者
第一作者
机构
刊名
分类号
参考文献
作者简介
基金资助
栏目信息

新锆合金最终退火处理工艺及其性能研究 被引量：2

Study on Final Annealing Process and Properties of New Zirconium Alloy
下载PDF
导出
摘要 通过制定锆合金的最终退火热处理工艺,研究了退火工艺参数对锆合金耐蚀性的影响,并对最终退火热处理后新锆合金的组织和性能进行了分析。结果发现,经最终退火热处理后锆合金的硬度变化不大,但耐腐蚀能力得到增强,其中铌元素的加入量为0.5%时效果相对较好。 The final annealing treatment of new zirconium alloy was made,and the influences of annealing treatment parameters on the corrosion resistance were studied. The microstructure and properties of the alloy were observed and analysed. The results show that the hardness of the alloy after final annealing treatment changes a little,but the corrosion resistance obviously improves,and the corrosion resistance is better when Nb content is 0.5%.
作者 王志远 范洪远 王鹏
机构地区 四川大学制造科学与工程学院 四川大学材料科学与工程学院
出处 《热加工工艺》 CSCD 北大核心 2010年第6期43-45,共3页 Hot Working Technology
关键词 新锆合金 最终退火热处理 极化曲线 耐腐蚀性能 new Zr-alloy final annealing treatment polarization curves corrosion resistance
分类号 TG146.414 [金属学及工艺—金属材料]
  • 相关文献

参考文献10

  • 1Kim Y S,Kim S K,Bang J G,et al.Efeets of Sn and Nb on massive hydriding kinetics of Zr-xSn-yNb alloy[J].Journal Nuclear Materals,2000,279:335-337.
  • 2Nikulina 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[A].Zirconium in the Nuclear Industry,Eleventh International Symposium[C].Philadephia PA:American Society for Testing and Materials,1996.785-802.
  • 3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
  • 4SharkeevYu P,Kozlov E V,Didenko A N,et al.Mechanisms of the long-range effect in metals and alloys by ion implantation[J].Surface and Coating Technology,1996,83:15-21.
  • 5Eadie R L,Ma Y,Jovanovie M T.An SEM study of b-phase decomposition during the annea-ling of Zr-2.5 Nb alloy[J].Journal Nuclear Materals,1997,244(2):141-145.
  • 6康永林.轧制工程学[M].北京:冶金工业出版社,2006.192-223.
  • 7李永良,宋教花,张涛.NbN沉积膜的抗腐蚀特性研究[J].真空科学与技术,2002,22(5):395-398. 被引量：2
  • 8Bentini G G,Berti M,Camera A,et al.Thermal oxidation of ion-implanted zirconium[J].Corrosion Science,1980,20:27-39.
  • 9Barberis P,Charquet D,Rebeyrolle V.Ternary Zr-Nb-Fe(O) system:phase diagram at 853 K and corrosion behaviour in the domain Nb《 0.8[J].Journal Nuclear Materials,2004,326(2-3):163-167.
  • 10Pecheur D,Godlewski J,Peybernes J,et al.Contribution to the understanding of the effect of water chemistry on the oxidation kinetics of zircaloy-4 cladding[A].Zirconium in the nuclear industry:Twelfth International Symposium[C].George P Sabol,Gerry D Moan:West Conshohcken,2000.793-801.

二级参考文献17

  • 1周邦新.Zr-Sn-Nb系合金的显微组织研究[C]..生物及环境材料 III2 1996中国材料研讨会文集[C].化学工业出版社,1997.187-191.
  • 2Foster J P,Dougherty J,Burke M Get al.Influence of Final Recrystallization Heat Treatment on Zircaloy-4 Strip Corrosion [J]. J Nucl Mat.1990,173:164-178.
  • 3Isobe T,Matsuo Y.Development of Highly Corrosion Resistant Zzirconium-base Alloys[C].Zirconium in the Nuclear Industry,Ninth International Symposium,ASTM STP 1132,in:Eucken C M and Grade A M Eds.America Society for Testing and Materials,Philadelphia,PA.1991. 346-367.
  • 4Kim Y S,Kim S K,Bang J Get al.Effects of Sn and Nb on Massive Hydriding Kinetics of Zr-XSn-YNb Alloy[J].J Nucl Mat.2000,279: 335-343.
  • 5Comstock R J,Schoenberger G,Sable G P.Influence of Processing Variables and Alloy Chemistry on the Corrosion Behavior of ZIRLO Nuclear Fuel Cladding[C].Zirconium in the Nuclear Industry,Eleventh International Symposium,ASTM STP 1295,in:Bradley E R and Sabol G P Eds.America Society for Testing and Materials,Philadelvhia,PA. 1996:710-725.
  • 6Nikulina 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 [C].Zirconium in the Nuclear Industry,Eleventh International Symposium,ASTM STP 1295,in:Bradley E R and Sabol G P Eds.America Society for Testing and Materials,Philadelphia,PA, 1996:785-804.
  • 7Mardon J P,Charquet D,Senevat J.Influence of Composition and Fabrication Process on out-of-Pile and in-Pile Properties of M5 Alloy[C].Zirconium in the Nuclear Industry,Twelfth International Symposium,ASTM STP 1354,in:Sabol G P and Moan G D Eds.America Society for Testing and Materials,West Conshobocken,PA,2000,505-524.
  • 8Choo K N,Kang Y H,Pyum S I,et al.Effect of Composition and Heat Treatment on the Microstructure and Corrosion Behavior of Zr-Nb Alloys [J].J Nucl Mat.1994,209:226-235.
  • 9Thorvaldsson T,Andersson T,Wilson Aet al.Correlation Between 400℃ Steam Corrosion Behavior,Heat Treatment,and Microstructure of Zircaloy-4 Tubing[C].Zirconium in the Nuclear Industry,Eighth International Symposium,ASTM STP 1023,in:Van Swam L F P and Eucken C M Eds,America Society for Testing and Materials.Philadelnhia.PA. 1989,128-140.
  • 10Zhou Bangxin,Zhao Wenjin,Miao Zhi et al.The Effect of Heat Treatment on the Corrosion Behavior of Zircaloy-4[R].China Nuclear Science and Technology Report,CNIC-01074,SINRE-0066,China Nuclear Informarion Center,Atomic Energy Press,1996.

共引文献19

同被引文献34

引证文献2

二级引证文献44

热加工工艺
2010年 第6期

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部