锆-4合金在高温水蒸汽中的氧化行为

中国腐蚀与防护学报

1991, Vol. 11

Issue (1): 99-104

研究报告

本期目录 | 过刊浏览

锆-4合金在高温水蒸汽中的氧化行为

陈鹤呜;马春来;何晓蓓;白新德

清华大学;清华大学;清华大学;清华大学

HIGH TEMPERATURE STEAM OXIDATION OF ZIRCALOY-4

Chen Heming Ma Chunlai He Xiaopei Bai Xinde (Tsinghun University)

全文: PDF(467 KB)

摘要: <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。

Abstract：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.

收稿日期: 1991-02-25

基金资助:国际原子能机构;;“七·五”攻关;;中科院腐蚀科学开放研究实验室资助课题

	服务

	把本文推荐给朋友
	加入引用管理器
	E-mail Alert
	RSS
	作者相关文章
	陈鹤呜
	马春来
	何晓蓓
	白新德
44.8K

引用本文:

陈鹤呜;马春来;何晓蓓;白新德. 锆-4合金在高温水蒸汽中的氧化行为[J]. 中国腐蚀与防护学报, 1991, 11(1): 99-104.
. HIGH TEMPERATURE STEAM OXIDATION OF ZIRCALOY-4. J Chin Soc Corr Pro, 1991, 11(1): 99-104.

链接本文:

https://www.jcscp.org/CN/ 或 https://www.jcscp.org/CN/Y1991/V11/I1/99

[1] Gazarolli.F.et al.,ASTM STP 754． P430～449(1982)
[2] 李铁藩.曲英哲.中国腐蚀与防护学报,8(1) ,21(1988)
[3] Pawel.R.E.et al.,ASTM STP 633． P119～113(1977)
[4] Baker.L.and Just,L.C.ANL-6548 May(1962)
[5] 陈鹤呜.马春来,核科学工程,No.1,(1982)

No related articles found!

Viewed

Full text

Abstract

Cited

Shared

Discussed