期刊文献+

Zr-Nb-Cu合金的水蒸气氧化行为研究

Research on Steam Oxidation Behavior of Alloy Zr-Nb-Cu
下载PDF
导出
摘要 研究了Zr-Nb-Cu合金在非等温和等温条件下的水蒸气氧化行为。结果表明,在非等温阶段,升温速度越高,合金的氧化质量增加越低,但在随后的等温阶段氧化质量增加越高。根据非等温阶段合金水蒸气氧化质量增加曲线,获得了氧化激活能与氧化质量增加之间的关系。另外,非等温阶段升温速度越大,氧化膜表面开裂现象越明显。 The steam oxidation behavior of the alloy Zr-Nb-Cu under non-isothermal and isothermal conditions was investigated. The results show that the oxidation mass gain decreases with the increase of temperature during non-isothermal process, but oxidation mass gain increases in the subsequent isothermal process. The relationship between oxidation activative energy and mass gain is obtained based on the mass grain curves of the alloy during non-isothermal process. Furthermore, the crack and bulge of oxidation film is more obvious with the increase of heating rate during non-isothermal process.
出处 《铸造技术》 CAS 北大核心 2015年第4期830-833,共4页 Foundry Technology
基金 国家高科技研究发展计划资助项目(2008AA031701)
关键词 Zr-Nb-Cu合金 非等温/等温 水蒸气氧化 激活能 微观组织 alloy Zr-Nb-Cu non-isothermal/isothermal steam oxidation acfivative energy microstructure
  • 相关文献

参考文献14

  • 1Nagase F,Otomo T,Uetsuka H.Oxidation Kinetics of Low-Sn Zircaloy-4 at the Temperature Range from 773 to 1573K[J].Journal of Nuclear Science and Techniques,2003,40(4):213-219.
  • 2Yan Y,Burtseva T A,Billone M C.High-temperature steam-oxidation behavior of Zr-1Nb cladding alloy E110[J].Journal of Nuclear Materials,2009,393(3):433-448.
  • 3Kim H G,Choi B K,Park J Y,et al.Influence of the manufacturing processes on the corrosion of Zr-1.1Nb-0.05Cu alloy[J].Corrosion science,2009,51(10):2400-2405.
  • 4Park K,Yang S,Ho K.The effect of high pressure steam on the oxidation of low-Sn Zircaloy-4 at temperatures between 700 and900°C[J].Journal of Nuclear Materials,2012,420(1-3):39-48.
  • 5Baek J H,Jeong Y H.Steam oxidation of Zr-1.5Nb-0.4Sn-0.2Fe-0.1Cr and Zircaloy-4 at 900-1200°C[J].Journal of Nuclear Materials,2007,361:30-40.
  • 6Urbanic V F,Heidrick T R.High-temperature oxidation of zircaloy-2 and zircaloy-4 in steam[J].Journal of Nuclear Materials,1978,75(2):251-261.
  • 7Jeong Y H,Park S Y,Lee M H,et al.Out-of-pile and in-pile perfomance of advanded zirconium alloys(HANA)for high burn-up fuel[J].Journal of Nuclear Science and Technology,2006,43(9):977-983.
  • 8Kawasaki S,Furuta T,Suzuki M.Oxidation of zircaloy-4 under high temperature steam atmosphere and its effect on ductility of cladding[J].Journal of Nuclear Science and Technology,1978,15(8):589-596.
  • 9Masaki A,Fumihisa N.The relationship between the amount of oxidation and activation energy on the steam oxidation reaction of Zircaloy-4 cladding[J].Journal of Nuclear Materials,2013,440(1-3):457-466.
  • 10Steinbrück M,Birchley J,Boldyrev A V,et al.High-temperature oxidation and quench behavior of Zircaloy-4and E110 cladding alloys[J].Progress in Nuclear Energy,2010,52(1):19-36.

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