首页> 外文会议>ASME turbo expo: turbine technical conference and exposition >STRESS CORROSION CRACKING AND CORROSION FATIGUE ANALYSIS OF NUCLEAR STEAM TURBINE ROTOR
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STRESS CORROSION CRACKING AND CORROSION FATIGUE ANALYSIS OF NUCLEAR STEAM TURBINE ROTOR

机译:核汽轮机转子的应力腐蚀开裂和腐蚀疲劳分析

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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.
机译:尽管应力腐蚀开裂(SCC)和腐蚀疲劳开裂可发生在核汽轮机的许多位置,但它们大多数是在低压圆盘边缘,转子槽和缩紧圆盘的键槽处引发的。对于核汽轮机组件,长寿命和高可用性是运行中非常重要的因素。通常运行超过60年的核电站都容易受到这种故障机制的影响。如果发生SCC或腐蚀疲劳,特别是在转子槽或键槽中,则会对核蒸汽轮机的寿命产生重大影响。在本文中,将建立的SCC的方法和汽轮机部件的腐蚀疲劳控制寿命预测方法用于评估在制造过程中遭受局部键槽表面损伤以及残余压应力损失的新缩孔盘。

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