STRESS CORROSION CRACKING AND CORROSION FATIGUE ANALYSIS OF NUCLEAR STEAM TURBINE ROTOR

被引:0
|
作者
Chen, Gang [1 ]
Jiang, Puning [1 ]
Ye, Xingzhu [1 ]
Zhang, Junhui [1 ]
Hu, Yifeng [1 ]
Hao, Zhenzhen [1 ]
机构
[1] Shanghai Elect Power Generat Equipment Co Ltd, Shanghai Turbine Plant, Shanghai, Peoples R China
关键词
TRANSITION; EVOLUTION; PIT;
D O I
暂无
中图分类号
U6 [水路运输]; P75 [海洋工程];
学科分类号
0814 ; 081505 ; 0824 ; 082401 ;
摘要
Although stress corrosion cracking (SCC) and corrosion fatigue cracking can occur in many locations of nuclear steam turbines, most of them initiate at low pressure disc rim, rotor groove and keyway of the shrunk-on disc. For nuclear steam turbine components, long life endurance and high availability are very important factors in the operation. Usually nuclear power plants operating more than sixty years are susceptible to this failure mechanism. If SCC or corrosion fatigue happens, especially in rotor groove or keyway, it has a major influence on nuclear steam turbine life. In this paper, established methods for the SCC and corrosion fatigue-controlled life prediction of steam turbine components were applied to evaluating a new shrunk-on disc that had suffered local keyway surface damage during manufacture and loss of residual compressive stress.
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页数:6
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