摘要
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。
Heat treatments with different parameters are performed on SA508-Ⅲ forging welding joints with submerged arc welding.The mechanical property tests,such as tension, impact and hardness tests,of the welding joints are carried out.Affecting laws of post-weld heat treatment on mechanical properties of SA508-Ⅲ, steel is discussed and analyzed on the basis of test results.The best range of holding time and temperature of post-weld heat treatment is recommended for SA508-Ⅲ, steel welding joint.
出处
《锅炉技术》
北大核心
1997年第1期12-16,22,共6页
Boiler Technology
