LOW CYCLE FATIGUE OF STEELS FOR NUCLEAR PRESSURE VESSELS IN HOT WATER.

被引:0
|
作者
Garnier, C.
Kowalczuk, G.
Roche, R.L.
Barrachin, B.
机构
关键词
STEEL; -; Fatigue;
D O I
暂无
中图分类号
学科分类号
摘要
The fatigue behavior of mechanical structures in the construction of nuclear reactors is important from both the safety and the reliability standpoints. It is in connection with nuclear reactors that fatigue analysis methods were introduced into the analysis of pressure vessels. A number of provisions relative to deterioration due to time, loads applied and the environment are examined.
引用
收藏
相关论文
共 50 条