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在三代非能动压水堆核电设备上,大量地使用到了SA-508Gr.3Cl.2钢,该材料具有较高的强度和低温冲击韧性。由于核电部件材料厚度大,SA-508Gr.3Cl.2钢焊接完成后需要进行较长时间的热处理,以消除残余应力。针对SA-508Gr.3Cl.2焊缝,选取了国内外不同牌号的四种埋弧焊焊丝焊剂进行焊接试验,并分别进行了不同焊后热处理保温时间下的焊缝金属拉伸和冲击试验。通过对试验结果的分析表明:焊后热处理后,SA-508 Gr.3Cl.2钢焊缝拉伸性能有较大程度的降低,随着焊后热处理时间的增长,焊缝强度降低的趋势逐渐减缓;焊后热处理对SA-508Gr.3Cl.2钢焊缝冲击性能影响无明显规律;随着焊后热处理时间的延长,焊缝基体组织未发生显著变化,晶间析出物有所增加并长大。焊缝的性能,特别是其低温冲击性能,更大程度取决于焊接参数,尤其是焊接热输入量。为获取理想的焊缝力学性能,需采用合适的焊接参数,控制热输入量。
SA-508Gr.3Cl.2 steel has been widely used in the three generations of non-active PWR nuclear power equipment. The material has high strength and low-temperature impact toughness. Due to the thick material of nuclear power components, SA-508Gr.3Cl.2 steel after welding is required for a long time heat treatment to eliminate residual stress. According to SA-508Gr.3Cl.2 welds, four types of submerged arc welding flux with different grades were selected for welding test. The tensile test and tensile test of weld metal with different post-weld heat treatment holding time were carried out respectively. The analysis of test results shows that the tensile properties of SA-508 Gr.3Cl.2 weld steel decrease to a great extent after the post-weld heat treatment, and the weld strength decreases gradually with the increase of post-weld heat treatment time The results showed that there was no obvious rule that the effect of post-weld heat treatment on the impact properties of SA-508Gr.3Cl.2 steel weld was obvious. With the prolonging of post-weld heat treatment time, there was no significant change in weld matrix structure, Big. Weld performance, especially its low temperature impact properties, depends more on the welding parameters, especially the welding heat input. In order to obtain the ideal mechanical properties of the weld, appropriate welding parameters are used to control the heat input.