首页> 外文会议>International Conference on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors >EFFECT OF STRAIN-HARDENING ON STRESS CORROSION CRACKING OF AISI 304L STAINLESS STEEL IN PWR PRIMARY ENVIRONMENT AT 360 deg C
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EFFECT OF STRAIN-HARDENING ON STRESS CORROSION CRACKING OF AISI 304L STAINLESS STEEL IN PWR PRIMARY ENVIRONMENT AT 360 deg C

机译:应变硬化对360℃的PWR初级环境中AISI 304L不锈钢应力腐蚀开裂的影响

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Austenitic stainless steels (ASS) are widespread in primary and auxiliary circuits of PWR plants because of their good resistance to general corrosion at elevated temperature. Nevertheless, some components suffer stress corrosion cracking (SCC) under neutron irradiation. In order to avoid complex and costly corrosion facilities, the increase of hardness induced by irradiation on the material is commonly simulated by applying a strain hardening on non-irradiated material prior to stress cracking tests. Stress corrosion tests were conducted corrosionon AISI 304L ASS in a PWR environment (360 deg C). Particular attention was directed towards pre-straining effects on crack growth rate (CGR) and crack growth path (CGP). Results and electronic microscope examinations (SEM & TEM) have demonstrated that the susceptibility of 304L to SCC in high-temperature hydrogenated water was enhanced by pre-straining. It seemed that IGSCC was enhanced by strain localization.
机译:由于它们在升高温度下良好的耐腐蚀性,奥氏体不锈钢(ASS)普遍存在PWR植物的初级和辅助电路中。然而,一些组件在中子辐射下遭受压力腐蚀裂纹(SCC)。为了避免复杂且昂贵的腐蚀设施,通常通过在应力开裂试验之前在非照射材料上施加菌株硬化来模拟材料的辐射诱导的硬度增加。在PWR环境中进行腐蚀腐蚀试验,在PWR环境中进行腐蚀剂AISI 304L ASS(360℃)。特别注意朝向裂纹生长速率(CGR)和裂纹生长途径(CGP)进行预调整作用。结果和电子显微镜检查(SEM&TEM)表明,通过预紧张增强了304L至SCC在高温氢化水中的敏感性。似乎通过应变局部化提高了IGSCC。

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