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对核容器采用国产SA508－Ⅲ钢锻件埋弧自动焊接头进行不同规范参数热处理，对接头的拉伸、冲击和硬度等力学性能进行了试验。根据试验结果，分析和讨论了焊后热处理对接头力学性能的影响，对SA508－Ⅲ钢提出了最佳焊后热处理保温温度和时间范围。
The nuclear vessel SA508-Ⅲ steel submerged arc welding automatic forging parameters of different specifications of the heat treatment, the joint tensile, impact and hardness and other mechanical properties were tested. According to the experimental results, the influence of post-weld heat treatment on the mechanical properties of the joint was analyzed and discussed. The best post-weld heat treatment temperature and time range for SA508-Ⅲ steel were proposed.