Thermographic investigation of the fatigue behavior of reactor pressure vessel steels

被引:114
|
作者
Yang, B [1 ]
Liaw, PK
Wang, H
Jiang, L
Huang, JY
Kuo, RC
Huang, JG
机构
[1] Univ Tennessee, Dept Mat Sci & Engn, Knoxville, TN 37996 USA
[2] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
[3] INER, Lungtan 325, Taiwan
[4] Taiwan Power Co, Nucl Operat Dept, Taipei 100, Taiwan
基金
美国国家科学基金会;
关键词
D O I
10.1016/S0921-5093(00)01910-9
中图分类号
TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
The fatigue behavior of reactor pressure vessel (RPV) steels during fatigue testing was monitored by an advanced, high-speed, high-sensitivity, nondestructive evaluation (NDE) technique called infrared (IR) thermography. Five stages of temperature profiles during fatigue were recorded: an initial increase of the mean specimen temperature followed by a temperature decrease, a constant (equilibrium) temperature region, an abrupt temperature increase, and a temperature drop after the specimen failure. Using the state-of-the-art IR camera, the temperature profiles were recorded cycle by cycle during 20 Hz fatigue testing. A theoretical model combining the thermoelastic, inelastic, and heat-conduction effects were used to explain and predict the temperature evolution during fatigue. Specifically, the temperature evolution was predicted, and the results were found to be in good agreement with the experimental data. (C) 2001 Elsevier Science B.V, All rights reserved.
引用
收藏
页码:131 / 139
页数:9
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