热老化对<strong>316LN</strong>力学性能和晶间腐蚀敏感性的影响

doi:10.11901/1005.3093.2022.367

材料研究学报

2023, Vol. 37

Issue (5): 381-390 DOI: 10.11901/1005.3093.2022.367

研究论文

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热老化对316LN力学性能和晶间腐蚀敏感性的影响

杨宝磊¹^,², 刘廷光²(

), 苏香林³, 范宇², 邱亮¹, 陆永浩²

^1.天津重型装备工程研究有限公司天津 300450
^2.北京科技大学国家材料服役安全科学中心北京 100083
^3.中国兵器工业集团内蒙古第一机械集团有限公司工艺研究所包头 014030

Effect of Thermal Aging on Mechanical Properties and Intergranular Corrosion Resistance of 316LN

YANG Baolei¹^,², LIU Tingguang²(

), SU Xianglin³, FAN Yu², QIU Liang¹, LU Yonghao²

^1.Tianjin Heavy Equipment Engineering Research Co., Ltd., Tianjin 300450, China
^2.National Center for Materials Service Safety, University of Science and Technology Beijing, Beijing 100083, China
^3.Research Institute of Processing Technology, Inner Mongolia First Machinery Group Co., Ltd., North Industries Group Co., Ltd., Baotou 014030, China

引用本文:

杨宝磊, 刘廷光, 苏香林, 范宇, 邱亮, 陆永浩. 热老化对316LN力学性能和晶间腐蚀敏感性的影响[J]. 材料研究学报, 2023, 37(5): 381-390.
Baolei YANG, Tingguang LIU, Xianglin SU, Yu FAN, Liang QIU, Yonghao LU. Effect of Thermal Aging on Mechanical Properties and Intergranular Corrosion Resistance of 316LN[J]. Chinese Journal of Materials Research, 2023, 37(5): 381-390.

全文: PDF(20122 KB) HTML

摘要:

将热锻固溶态316LN不锈钢试样在400℃空气中热老化处理400~10000 h，使用金相显微镜、扫描电子显微镜(SEM)、电子背散射衍射(EBSD)和X射线衍射(XRD)等手段分析了固溶态及热老化试样的显微组织，用小冲杆、纳米压痕和维氏硬度测试研究了热老化对这种材料力学性能的影响；用草酸电解侵蚀方法进行晶间腐蚀试验，用EBSD和原子力显微镜(AFM)定量分析了热老化对各类型晶界晶间腐蚀敏感性的影响。结果表明，在400℃热老化10000 h后316LN不锈钢的微米级显微组织、晶粒尺寸、晶界形貌和晶界特征分布都没有明显的变化。但是，热老化使晶粒的晶格常数变小，其原因是固溶在晶粒内的间隙原子和位错等向晶界处扩散迁移，使材料的强度和硬度提高而塑性和抗晶间腐蚀性能降低。各类型晶界的晶间腐蚀敏感性都随着热老化时间的延长而提高，但是CSL晶界的晶间腐蚀敏感性低于随机晶界。

关键词 ：金属材料, 316LN不锈钢, 热老化, 小冲杆, 晶间腐蚀, CSL晶界

Abstract：

Nitrogen enhanced low carbon 316LN stainless steel, as a single-phase austenitic stainless steel, is selected as a candidate material of primary pipe for the third-generation pressurized water reactors. In the present work, the solution annealed 316LN was thermal aged at 400℃ for 400, 1000, 5000 and 10000 hours, respectively. The microstructures of the solution annealed and thermal aged steels were compared by optical microscope, scanning electron microscope (SEM), electron backscatter diffraction (EBSD) and X-ray diffraction (XRD). The effect of thermal aging on mechanical properties of the steels was evaluated by using small punch test, nanoindentation and microhardness tester. The intergranular corrosion resistance of the steels was measured by using electrolytic etching in oxalic acid solution, and the effect of thermal aging on the corrosion resistance of various types of grain boundaries were characterized by using EBSD and atomic force microscope (AFM). The results show that thermal aging at 400℃ for 10000 h will not cause microstructural changes in the micron level of 316LN stainless steel. No change was observed in grain size, grain boundary morphology and characteristics of grain boundary distribution, and no new phase was formed during thermal aging. However, after thermal aging, the lattice parameter becomes smaller, which may be ascribed to that the interstitial atoms and dislocations originally dissolved in grains diffused and migrated towards the grain boundaries. This may result in changes of the mechanical properties of the 316LN, including the increase of strength and hardness, and the lower of plasticity and intergranular corrosion resistance. The intergranular corrosion susceptibilities of all types of grain boundaries increase with the extension of thermal aging time, but the susceptibility of coincidence site lattice (CSL) grain boundaries is always lower than that of random grain boundaries. Hence grain boundary engineering, which is a thermomechanical process and could produce high fraction of low-∑CSL grain boundaries in materials, could be applied to mitigate the intergranular corrosion of 316LN.

Key words： metallic materials 316LN stainless steel thermal aging small punch test intergranular corrosion CSL grain boundary

收稿日期: 2022-07-06

ZTFLH:

TG142.71

基金资助:国家重点研发计划(2019YFB1900905);中央高校基本科研业务费专项(FRF-TP-20-019A3)

作者简介: 杨宝磊，男，1996年生

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https://www.cjmr.org/CN/10.11901/1005.3093.2022.367 或 https://www.cjmr.org/CN/Y2023/V37/I5/381

图1 小冲杆实验装置

图2 316LN在400℃热老化不同时间后的金相照片和扫描图

图3 始态和热老化不同时间后316LN不锈钢的晶界网络图

图4 始态和热老化不同时间试样的晶界特征分布

图5 热老化不同时间后316LN不锈钢的XRD谱

图6 热老化不同时间试样的位移-载荷曲线

图7 热老化不同时间试样的小冲杆性能变化

图8 热老化不同时间试样的小冲杆断口形貌

图9 热老化不同时间试样的纳米压痕性能和显微维氏硬度

图10 热老化不同时间试样的晶间腐蚀形貌

图11 热老化10000 h试样晶间腐蚀后的原子力显微镜分析

图12 晶间腐蚀沟深度的AFM测试图

表1 不同热老化时间和不同类型晶界的腐蚀深度

1	Shu G G, Lu N W. Aging problems and life evaluation for the key metallic components in PWR nuclear power plant [J]. Electr. Power, 2006(05): 53
1	束国刚, 陆念文. 压水堆核电厂关键金属部件的老化和寿命评估 [J]. 中国电力, 2006(05): 53
2	Wang X T, Li S L. Research status and development trend of nuclear power steel [J]. Adv. Mater. Ind., 2014(07): 2
2	王西涛, 李时磊. 核电用钢的研究现状及发展趋势 [J]. 新材料产业, 2014(07): 2
3	Fan Y, Liu T G, Xin L, et al. Thermal aging behaviors of duplex stainless steels used in nuclear power plant: A review [J]. J. Nucl. Mater., 2021, 544: 152693 doi: 10.1016/j.jnucmat.2020.152693
4	Li S, Wang Y, Wang X, et al. G-phase precipitation in duplex stainless steels after long-term thermal aging: A high-resolution transmission electron microscopy study [J]. J. Nucl. Mater., 2014, 452: 382 doi: 10.1016/j.jnucmat.2014.05.069
5	Schwarm S C, Mburu S, Kolli R P, et al. Effects of long-term thermal aging on bulk and local mechanical behavior of ferritic-austenitic duplex stainless steels [J]. Materials Science and Engineering: A, 2018, 720: 130 doi: 10.1016/j.msea.2018.02.058
6	Zhang H, Li S L, Liu G, et al. Effects of hot working on the microstructure and thermal ageing impact fracture behaviors of Z3CN20-09M duplex stainless steel [J]. Acta Metall. Sin., 2017, 53: 531
6	张海, 李时磊, 刘刚等. 热加工对Z3CN20-09M双相不锈钢组织及热老化冲击断裂行为的影响 [J]. 金属学报, 2017, 53: 531
7	Yao Y H, Wei J F, Wang Z P. Effect of long-term thermal aging on the mechanical properties of casting duplex stainless steels [J]. Materials Science and Engineering: A, 2012, 551: 116 doi: 10.1016/j.msea.2012.04.105
8	Li S L, Wang Y L, Zhang H L, et al. Microstructure evolution and impact fracture behaviors of Z3CN20-09M stainless steels after long-term thermal aging [J]. J. Nucl. Mater., 2013, 433: 41 doi: 10.1016/j.jnucmat.2012.09.004
9	Guo C, Yu D, Sun X, et al. Fatigue failure mechanism and life prediction of a cast duplex stainless steel after thermal aging [J]. Int. J. Fatigue., 2021, 146: 106161 doi: 10.1016/j.ijfatigue.2021.106161
10	Xue F, Wang Z X, Shu G, et al. Thermal aging effect on Z3CN20.09M cast duplex stainless steel [J]. Nucl. Eng. Des., 2009, 239: 2217 doi: 10.1016/j.nucengdes.2009.06.009
11	Chen Y, Yang B, Zhou Y, et al. Evaluation of pitting corrosion in duplex stainless steel Fe20Cr9Ni for nuclear power application [J]. Acta Mater., 2020, 197: 172 doi: 10.1016/j.actamat.2020.07.046
12	Li S L, Wang Y L, Wang H, et al. Effects of long-term thermal aging on the stress corrosion cracking behavior of cast austenitic stainless steels in simulated PWR primary water [J]. J. Nucl. Mater., 2016, 469: 262 doi: 10.1016/j.jnucmat.2015.11.043
13	Cicero S, Setién J, Gorrochategui I. Assessment of thermal aging embrittlement in a cast stainless steel valve and its effect on the structural integrity [J]. Nucl. Eng. Des., 2009, 239: 16 doi: 10.1016/j.nucengdes.2008.09.009
14	Chandra K, Singhal R, Kain V, et al. Low temperature embrittlement of duplex stainless steel: Correlation between mechanical and electrochemical behavior [J]. Materials Science and Engineering: A, 2010, 527: 3904 doi: 10.1016/j.msea.2010.02.069
15	Wang M J, Chen L, Liu X C, et al. Influence of thermal aging on the SCC susceptibility of wrought 316LN stainless steel in a high temperature water environment [J]. Corros. Sci., 2014, 81: 117 doi: 10.1016/j.corsci.2013.12.011
16	Wang Y Q, Yang B, Han J, et al. Localized corrosion of thermally aged cast duplex stainless steel for primary coolant pipes of nuclear power plant [J]. Procedia Engineering, 2012, 36: 88 doi: 10.1016/j.proeng.2012.03.015
17	Chung H M. Aging and life prediction of cast duplex stainless steel components [J]. International Journal of Pressure Vessels and Piping, 1995, 50(1~3), 179
18	Pumphrey P H, Akhurst K N. Aging kinetics of CF3 cast stainless steel in temperature range 300~400℃ [J]. Materials Science and Technology, 1990, 6, 211 doi: 10.1179/mst.1990.6.3.211
19	Zhang Q, Singaravelu A S S, Zhao Y, et al. Mechanical properties of a thermally-aged cast duplex stainless steel by nanoindentation and micropillar compression [J]. Materials Science and Engineering: A, 2019, 743: 520 doi: 10.1016/j.msea.2018.11.112
20	Brandon D G. The structure of high-angle grain boundaries [J]. Acta Metall., 1966, 14(11): 1479 doi: 10.1016/0001-6160(66)90168-4
21	Wang J W, Chen Y B, Zhu Q, et al. Grain boundary dominated plasticity in metallic materials [J]. Acta Metall. Sin., 2022, 58: 726
21	王江伟, 陈映彬, 祝祺等. 金属材料的晶界塑性变形机制 [J]. 金属学报, 2022, 58: 726 doi: 10.11900/0412.1961.2021.00594
22	Wang M J, Ma Q, Li J L, et al. Influence of thermal aging on microstructure and mechanical properties of nuclear grade 316LN forged austenitic stainless steel [J]. J. Yanshan Univ., 2013, 37(05): 385
22	王明家, 马千, 李景丽等. 热老化对核级316LN锻造控氮奥氏体不锈钢微观组织及性能的影响 [J]. 燕山大学学报. 2013, 37(05):385
23	Cao X Y, Zhu P, Liu T G, et al. Thermal aging effects on mechanical and electrochemical properties of stainless steel weld overlay cladding [J]. Surf. Coat Tech., 2018, 344: 111 doi: 10.1016/j.surfcoat.2018.02.046
24	Altstadt E, Ge H E, Kuksenko V, et al. Critical evaluation of the small punch test as a screening procedure for mechanical properties [J]. J. Nucl. Mater., 2016, 472: 186 doi: 10.1016/j.jnucmat.2015.07.029
25	Zhu Q, Cao G, Wang J W, et al. In situ atomistic observation of disconnection-mediated grain boundary migration [J]. Nat. Commun., 2019, 10(1): 1 doi: 10.1038/s41467-018-07882-8
26	Zhu Q, Zhou H F, Chen Y B, et al. Atomistic dynamics of disconnection-mediated grain boundary plasticity: A case study of gold nanocrystals [J]. J. Mater. Sci. Technol., 2022, 125(1):182 doi: 10.1016/j.jmst.2022.02.040
27	Luo Q, Wang L, Liu S W, et al. Tendence of thermal aging embrittlement of weld of primary pipe made of 316LN stainless stell in nuclear power plant [J]. J. Iron Steel Res., 2015, 27: 4
27	罗强, 王理, 刘思维等. 核电主管道用316LN不锈钢焊缝热老化脆化的趋势 [J]. 钢铁研究学报. 2015, 27: 4
28	Hong S H, Seo M G, Jang C H, et al. Evaluation of the effects of thermal aging of austenitic stainless steel welds using small punch test [J]. Procedia Eng., 2015, 130: 1010 doi: 10.1016/j.proeng.2015.12.253
29	Fujii T, Suzuki M, Shimamura Y. Susceptibility to intergranular corrosion in sensitized austenitic stainless steel characterized via crystallographic characteristics of grain boundaries [J]. Corros Sci., 2022, 195: 109946 doi: 10.1016/j.corsci.2021.109946
30	Liu T G, Xia S, Bai Q, et al. Three-dimensional study of grain boundary engineering effects on intergranular stress corrosion cracking of 316 stainless steel in high temperature water [J]. J. Nucl. Mater., 2018, 498: 290 doi: 10.1016/j.jnucmat.2017.10.004
31	Hong Y B, Kokawa H, Zhang J W, et al. Suppression of chromium depletion by grain boundary structural change during twin-induced grain boundary engineering of 304 stainless steel [J]. Scr. Mater., 2003(49): 219
32	Kokawa H, Watanabe T, Karashima S. Dissociation of lattice dislocations in coincidence boundaries [J]. J. Mater. Sci., 1983, 18(4):1183 doi: 10.1007/BF00551988
33	Kokawa H, Watanabe T, Karashima S. Structural changes during sliding of aluminium grain boundaries with different initial structures [J]. Scr. Metall., 1983, 17(10)
34	Watanabe T. An approach to grain boundary design for strong and ductile polycrystals [J]. Res Mech, 1984, 11: 47
35	Xia S, Zhou B X, Chen W J, Effect of deformation and heat-treatments on the grain boundary character distribution for 690 alloy [J]. Rare Met. Mater. Eng.. 2008, (06): 999
35	夏爽, 周邦新, 陈文觉. 形变及热处理对690合金晶界特征分布的影响 [J]. 稀有金属材料与工程, 2008, (06): 999
36	Gao X, Wang M L, Liu T G, et al. Investigation on thermo-mechanical processing and intergranular corrosion of TP347H stainless steel [J]. Mater. Sci. Tech, 2021, 37: 909 doi: 10.1080/02670836.2021.1963917
37	Shi F, Tian P C, Jia N, et al. Improving intergranular corrosion resistance in a nickel-free and manganese-bearing high-nitrogen austenitic stainless steel through grain boundary character distribution optimization [J]. Corros Sci., 2016, 107: 49 doi: 10.1016/j.corsci.2016.02.019
38	Tokita S, Kokawa H, Kodama S, et al. Suppression of intergranular corrosion by surface grain boundary engineering of 304 austenitic stainless steel using laser peening plus annealing [J]. Mater. Today Commun., 2020, 25: 101572

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