首页> 外文会议>International Conference on Environmental degradation of Materials in Nuclear Power Systems-Water Reactors >BEHAVIOR OF STRESS CORROSION CRACKING FOR TYPE 316LSTAINLESS STEEL WITH CONTROLLED DISTRIBUTION OF SURFACE WORK HARDENED LAYER IN SIMULATED BOILING WATER REACTORS ENVIRONMENT
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BEHAVIOR OF STRESS CORROSION CRACKING FOR TYPE 316LSTAINLESS STEEL WITH CONTROLLED DISTRIBUTION OF SURFACE WORK HARDENED LAYER IN SIMULATED BOILING WATER REACTORS ENVIRONMENT

机译:316L不锈钢应力腐蚀裂缝的行为,采用模拟沸水反应器环境下表面工作硬化层的控制分布

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Stress corrosion cracking (SCC) of Type 316L stainless steels with controlled surface hardnessdistribution was investigated under simulated boiling water reactor (BWR) condition by crevicedbent beam (CBB) tests. Intergranular microcracks having a depth of less than 50 μm areobserved in 50 hours. Until 250 hours, depths of the microcracks are not increased. After 500hours, cracks with depths of more than 50 μm are observed. SCC is initiated preferentially in asteep hardness gradient area.
机译:通过CrevicedBent Beam(CBB)测试在模拟沸水反应器(BWR)条件下研究了316L不锈钢型具有受控表面硬度的316L不锈钢的应力腐蚀裂纹(SCC)。在50小时内,晶体微裂纹的深度小于50μm。直到250小时,微裂纹的深度不会增加。 500小时后,观察到具有50μm的深度的裂缝。 SCC优先于Astep硬度梯度区域启动。

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