Effects of grain boundary engineering treatment on fretting wear behavior of Inconel 690TT alloy
HAN Yong-ming1, HAN Jun-ling1, XIN Long1, LIU Ting-guang1, LU Yong-hao1, SHOJI Tetsuo1,2
1. National Center for Materials Service Safety, University of Science and Technology Beijing, Beijing 100083, China;
2. New Industry Creation Hatchery Center, Tohoku University, Sendai 980-8579, Japan
Abstract：The grain boundary engineering (GBE) treatment of heat treatment and cold rolling was adopted.The fretting wear behavior of Inconel 690TT alloy in air at room temperature and 320 ℃ was studied by OM, SEM, EBSD and white light interferometer. The results show that the proportion of low-∑ CSL boundaries of the best GBE sample is more than 70%, which is produced after 5% cold rolling,high temperature and short time annealing. The wear volumes and friction coefficients of the Inconel 690TT alloy samples at room temperature and 320 ℃ decrease with the increase of hardness and increase with the increase of grain size and low-∑ CSL boundary fraction. The fretting zone characteristic of Inconel 690TT alloy samples with larger grain sizes and higher proportion of low-∑ CSL boundaries under the same fretting experimental parameters is prone to full sliding, whereas it tends to partial sliding. Compared with grain size, the low-∑ CSL boundary fraction plays a more important role in determining the fretting behavior of GBE samples. The sample with higher fraction of low-∑ CSL boundaries has lower resistance to fretting wear, so GBE treatment is inimical to improving the fretting wear resistance of materials.
 ZINKLE S J,WAS G S.Materials challenges in nuclear energy[J].Acta Materialia,2013,61(3):735-758.
 张兴田.核电厂设备典型腐蚀损伤及其防护技术[J].腐蚀与防护,2016,37(7):527-533. ZHANG X T.Corrosion damage cases and corrosion protection technology of components in nuclear power plant[J].Corrosion & Protection,2016,37(7):527-533.
 唐辉.世界核电设备与结构将长期面临的一个问题——微动损伤[J].核动力工程,2000,21(3):221-226. TANG H.Fretting damage,one of world-wide difficulties in the field of nuclear power equipment and structures for a long-term[J].Nuclear Power Engineering,2000,21(3):221-226.
 WATANABE T.An approach to grain boundary design of strong and ductile polycrystals[J].Res Mechanica,1984,11(1):47-84.
 LEHOCKEY E M,LIMOGES D,PALUMBO G,et al.On improving the corrosion and growth resistance of positive Pb-acid battery grids by grain boundary engineering[J].Journal of Power Sources,1999,78(1/2):79-83.
 LIU T, XIA S,SHOJI T,et al The topology of three-dimensional grain boundary network and its influence on stress corrosion crack propagation characteristics in austenitic stainless steel in a simulated BWR environment[J].Corrosion Science,2017,129:161-168.
 HU C,XIA S,LI H,et al.Improving the intergranular corrosion resistance of 304 stainless steel by grain boundary network control[J].Corrosion Science,2011,53(5):1880-1886.
 LIU T,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].Journal of Nuclear Materials,2018,498:290-299.
 TELANG A,GILL A S,KUMAR M,et al.Iterative thermomechanical processing of alloy 600 for improved resistance to corrosion and stress corrosion cracking[J].Acta Materialia,2016,113:180-193.
 LIU T, XIA S, BAI Q, et al. Evaluation of grain boundary network and improvement of intergranular cracking resistance in 316L stainless steel after grain boundary engineering[J].Materials,2019,12(2):242.
 MICHIUCHI M,KOKAWA H,WANG Z J,et al.Twin-induced grain boundary engineering for 316 austenitic stainless steel[J].Acta Materialia,2006,54(19):5179-5184.
 XIN L,YANG B B,WANG Z H,et al.Effect of normal force on fretting wear behavior and mechanism of alloy 690TT in high temperature water[J].Wear,2016,210:368-369.
 PARK G S,KIM G G,KIM S J.Sliding wear behaviors of steam generator tube materials in high temperature water environment[J].Journal of Nuclear Materials,2006,352(1/3):80-84.
 HONG J K,KIM I S,PARK C Y,et al.Microstructural effects on the fretting wear of Inconel 690 steam generator tube[J].Wear, 2005,259(1):349-355.
 YUN J Y,SHIN G S,KIM D I,et al.Effect of carbide size and spacing on the fretting wear behavior of Inconel 690 SG tube mated with SUS 409[J].Wear,2015,338/339:252-257.
 LI J,LU Y,ZHANG H,et al.Effect of grain size and hardness on fretting wear behavior of Inconel 600 alloys[J].Tribology International,2015,81:215-222.
 李慧,夏爽,周邦新,等.镍基690合金时效过程中晶界碳化物的形貌演化[J].金属学报,2009,45(2):195-198. LI H,XIA S,ZHOU B X,et al.Evolution of carbide morphology precipitated at grain boundaries in Ni-based alloy 690[J].Acta Metallurgica Sinica,2009,45(2):195-198.
 LIU T,XIA S,LI H,et al.The highly twinned grain boundary network formation during grain boundary engineering[J].Materials Letters,2014,133:97-100.
 ZHUO Z,XIA S,BAI Q,et al.The effect of grain boundary character distribution on the mechanical properties at different strain rates of a 316L stainless steel[J].Journal of Materials Science,2018,53(4):2844-2858.
 VARENBERG M,HALPERIN G,ETSION I.Different aspects of the role of wear debris in fretting wear[J].Wear,2002,252(11/12):902-910.
 辛龙,李杰,陆永浩,等.Inconel 690合金高温微动磨损特性研究[J].摩擦学学报,2015,35(4):470-476. XIN L,LI J,LU Y H,et al.Fretting wear properties of Inconel 690 alloy at elevated temperature[J].Tribology,2015,35(4):470-476.
 ZHU M H,ZHOU Z R.On the mechanisms of various fretting wear modes[J].Tribology International,2011,44(11):1378-1388.
 HONG J K,KIM I S.Environment effects on the reciprocating wear of Inconel 690 steam generator tubes[J].Wear,2003,255(7/12):1174-1182.
 辛龙,马妙,陆永浩.Inconel600合金高温微动磨损特性[J].工程科学学报,2015,37(7):928-935. XIN L,MA M,LU Y H.Fretting wear properties of Inconel600 alloy at high temperature[J].Chinese Journal of Engineering,2015,37(7):928-935.
 屈盛官,王光宏,李文龙,等.高性能渗氮钢微动磨损性能研究[J].摩擦学学报,2012,32(5):486-492. QU S G,WANG G H,LI W L,et al.Fretting wear of a high-performance plasma nitrided steel[J].Tribology,2012,32(5):486-492.