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主管道焊接热影响区(HAZ)的应力腐蚀断裂(SCC)是压水堆核电站压力边界完整性的重要失效形式。本试验采用慢应变速率加载方式在二种高温水条件下研究三种不锈钢主管道焊接配偶HAZ的SCC行为,即316—316(编号1X),321—316(编号2X),321—321(编号3X),二种牌号不锈钢的化学成份列入表1,试验条件列入表2。由材料的环境力学性能变化并经归一处理得到SCC敏感指数I_(DS),将环境断裂吸收能经归
The stress corrosion cracking (SCC) of the main pipe HAZ is an important failure mode of the pressure boundary integrity of PWR nuclear power plant. In this experiment, the SCC behavior of HAZ of three kinds of stainless steel main pipe welding splices was studied under two kinds of high-temperature water conditions with slow strain rate loading, namely 316-316 (code 1X), 321-316 (code 2X), 321-321 3X), two grades of stainless steel chemical composition included in Table 1, the test conditions are listed in Table 2. From the change of environmental mechanical properties of the material, the SCC sensitivity index I_ (DS)