<正> 一、前言Zr-4合金具有优良的物理性能、机械性能,良好的耐蚀性、较低的吸氢率,在现今反应堆的建造中用作压水堆燃料元件的包壳材料。早在五十年代,人们就开始研究 Zr 合金与水蒸汽反应以制定核反应堆安全规则。世界上发生的核电站事故更加显示了制定核安全的迫切性。因而研究在失水事故状态下燃料包壳的氧化行为对于充分利用核能,制定正确的核反应堆安全运行规则具有重要的意义。
Oxidation behavior of zircaloy-4 in 1000℃～1400℃ flowing steam was studied, and rate laws of the weight-gain as well as the growth of the oxide and alpha layers were obtained.Weight-gain and thickness growth of the oxide layer in general followed the parabolic rate laws.In the long term oxidation at temperatures above 1225℃,the isother- mal oxidation,curve of zircaloy-4 transformed in shape during oxidation.The dependence of the weight-gain and thickness growth rate laws on temperature observed the Arrhenius Equation.Also conducted was the measurement of stress change during oxidation at tem- perature of 650℃～800℃ for zirconium and zircaloy-4 by a bending method.The struc- ture and composition of the oxide films were examined under AES and SEM.
参考文献
| [1] |
- 下载量()
- 访问量()
- 您的评分：
-
10%
-
20%
-
30%
-
40%
-
50%