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研究了锻后固溶处理和锻后去应力处理对核电主管道用316LN不锈钢的显微组织、残余应变和常温力学性能的影响,并研究了不同锻后热处理工艺对316LN不锈钢在沸腾的42%(质量分数)Mg Cl2溶液中应力腐蚀开裂(SCC)敏感性的影响。结果表明,固溶处理能够降低材料的屈服强度和消除锻造过程中的残余应变;锻后固溶处理和锻后去应力处理的样品分别在沸腾Mg Cl2溶液中浸泡24,48和72 h后均发生明显的穿晶应力腐蚀开裂(TGSCC);浸泡72 h后,锻后去应力处理的样品已经完全开裂,而锻后固溶处理的样品只有部分区域发生SCC开裂,即SCC敏感性较低。最后从屈服强度和残余应变角度讨论了锻后热处理对不锈钢SCC敏感性的影响机制。
The effect of forging treatment and forging treatment on the microstructure, residual strain and mechanical properties at room temperature of 316LN stainless steel for the main pipe of nuclear power plant were investigated. The effects of heat treatment on the mechanical properties of 316LN stainless steel in 42% (Mass fraction) MgCl2 solution stress corrosion cracking (SCC) sensitivity. The results show that the solution treatment can reduce the yield strength of the material and eliminate the residual strain during the forging process; after forging solution treatment and after forging treatment, the specimens were immersed in boiling MgCl 2 solution for 24, 48 and 72 h respectively Obvious stress corrosion cracking (TGSCC) occurred. After soaking for 72 h, samples subjected to stress treatment had completely cracked after forging treatment, but SCC cracking occurred only in some areas after forging treatment, that is, the sensitivity of SCC was low. Finally, the mechanism of heat treatment after forging on the sensitivity of stainless steel SCC was discussed from the point of yield strength and residual strain.