锻后热处理对核级316LN不锈钢在沸腾MgCl<sub>2</sub>溶液中应力腐蚀行为的影响

doi:10.11902/1005.4537.2014.223

中国腐蚀与防护学报

2015, Vol. 35

Issue (6): 488-495 DOI: 10.11902/1005.4537.2014.223

研究报告

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锻后热处理对核级316LN不锈钢在沸腾MgCl₂溶液中应力腐蚀行为的影响

郭跃岭^1,²,韩恩厚^1,²(

),王俭秋¹

1. 中国科学院金属研究所中国科学院核用材料与安全评价重点实验室沈阳 110016
2. 北京科技大学国家材料服役安全科学中心北京 100083

Effect of Post-forging Heat Treatment on Stress Corrosion Cracking of Nuclear Grade 316LN Stainless Steel in Boiling MgCl₂ Solution

Yueling GUO^1,²,En-Hou HAN^1,²(

),Jianqiu WANG¹

1. Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
2. National Center for Materials Service Safety, University of Science and Technology Beijing, Beijing 100083, China

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摘要:

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) MgCl₂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MgCl₂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。

关键词 ：不锈钢, 核电材料, 热处理, 应力腐蚀开裂, MgCl2溶液, 断口

Abstract：

Effect of post solution- and stress relief-treatment on the stress corrosion cracking (SCC) resistance via U-bend specimens test in 42% boiling MgCl₂ solution, as well as the microstructure, residual strain and mechanical properties of the forged 316LN stainless steel was studied. Results showed that the yield stress was reduced and the residual strain was eliminated through post solution-treatment for the forged steel. After immersion in boiling MgCl₂ solution for 24, 48 and 72 h, respectively, all the U-bend specimens of either the solution-treated or the stress relief-treated steels suffered from clearly transgranular stress corrosion cracking (TGSCC). Furthermore, of which all the stress relief-treated specimens were entirly cracked, while the solution-treated specimens were only locally cracked after immersion for 72 h, suggesting higher SCC resistance for the forged steel after a proper post solution-treatment. Finally, the mechanism of the effect of post-heat treatments on the SCC resistance was discussed in terms of the residual strain and yield stress of the forged steel.

Key words： stainless steel nuclear materials heat treatment stress corrosion cracking magnesium chloride solution fractography

基金资助:国家科技重大专项项目 (2011ZX06004-009) 资助

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引用本文:

郭跃岭,韩恩厚,王俭秋. 锻后热处理对核级316LN不锈钢在沸腾MgCl₂溶液中应力腐蚀行为的影响[J]. 中国腐蚀与防护学报, 2015, 35(6): 488-495.
Yueling GUO, En-Hou HAN, Jianqiu WANG. Effect of Post-forging Heat Treatment on Stress Corrosion Cracking of Nuclear Grade 316LN Stainless Steel in Boiling MgCl₂ Solution. Journal of Chinese Society for Corrosion and protection, 2015, 35(6): 488-495.

链接本文:

https://www.jcscp.org/CN/10.11902/1005.4537.2014.223 或 https://www.jcscp.org/CN/Y2015/V35/I6/488

表1 316LN不锈钢的室温力学性能

图 1 316LN不锈钢的室温拉伸断口形貌

图2 316LN不锈钢的显微组织

图3 由EBSD测得的316LN不锈钢的晶粒尺寸分布

图4 316LN不锈钢内部夹杂物

表2 由EDS-SEM得到的S41和S42内部夹杂物的化学成分

图5 由EBSD得到的316LN不锈钢的LAM分布图

图6 SCC实验之前U型样品的实物图和样品最底端表面的SEM像

图7 U型316LN不锈钢样品在沸腾MgCl2溶液中浸泡72 h后底部表面的SCC裂纹形貌

图8 316LN不锈钢在沸腾的42%MgCl2溶液中浸泡不同时间后的宏观SCC断口形貌

图9 U型样品在沸腾MgCl2溶液中浸泡72 h后的SCC断口SEM像

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