The subsurface damage mechanism of Inconel 690 during fretting wear in pure water

2018 ◽  
Vol 117 ◽  
pp. 152-161 ◽  
Author(s):  
J. Li ◽  
Y.H. Lu ◽  
L. Xin ◽  
T. Shoji
Keyword(s):  
Pure Water ◽  
Damage Mechanism ◽  
Subsurface Damage ◽  
Fretting Wear ◽  
Inconel 690

The damage mechanism of Alloy 690TT against Alloy 600 caused by fretting wear in room temperature pure water

2020 ◽  
Vol 161 ◽  
pp. 110176 ◽  
Author(s):  
Long Xin ◽  
Qian Huang ◽  
Yongming Han ◽  
Yonghao Lu ◽  
Weidong Zhang ◽  
...  
Keyword(s):  
Room Temperature ◽  
Pure Water ◽  
Damage Mechanism ◽  
Fretting Wear ◽  
Alloy 600

Study on the Fretting Wear Behavior and Mechanism of Nuclear Alloy 690 Tube

2012 ◽  
Vol 512-515 ◽  
pp. 1740-1746
Author(s):  
Jin Na Mei ◽  
Fei Xue ◽  
Zhao Xi Wang ◽  
Guo Dong Zhang ◽  
Lei Huang ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Wear Behavior ◽  
Damage Mechanism ◽  
Fretting Wear ◽  
Composition Analysis ◽  
Ambient Conditions ◽  
Inconel 600 ◽  
Delamination Wear ◽  
Slip Regime ◽  
Inconel 690

The fretting wear behavior of Inconel 690 for steam generator tube in a nuclear power plant against Inconel 600 (Cr plating) for anti-vibration bar was investigated in a plain cylinder/plane contact configuration under ambient conditions. The fretting wear tests were conducted under various applied normal loads of 20-100 N, slip amplitudes of 20-100 μm and frequency of 2 Hz. Observation of worn surface and corresponding chemical composition analysis were performed to clarify the fretting wear mechanism. It is found that the friction coefficient value increases firstly and then tends to stabilize with decrease in normal loads and increase in slip amplitudes. In addition, the fretting regime is identified to be gross slip regime, indicating that the fretting damage mechanism of Inconel 690 tube against Inconel 600 (Cr plating) bar is wear. The corresponding fretting wear mechanisms are dominant by delamination wear, abrasive wear and friction oxidation.

Effect of carbide size and spacing on the fretting wear behavior of Inconel 690 SG tube mated with SUS 409

Wear ◽  
2015 ◽  
Vol 338-339 ◽  
pp. 252-257 ◽  
Author(s):  
Jae Yong Yun ◽  
Gyeong Su Shin ◽  
Dae Il Kim ◽  
Ho Sik Lee ◽  
Woong Soon Kang ◽  
...  
Keyword(s):  
Wear Behavior ◽  
Fretting Wear ◽  
Inconel 690 ◽  
Carbide Size

Wear Transitions of Tube-Support Components for a Nuclear Steam Generator under Fretting Conditions

2006 ◽  
Vol 326-328 ◽  
pp. 1263-1266 ◽  
Author(s):  
Sung Hoon Jeong ◽  
Jung Min Park ◽  
Joong Hui Lee ◽  
Young Ze Lee
Keyword(s):  
Nuclear Power ◽  
Applied Load ◽  
Fluid Flows ◽  
Relative Displacement ◽  
Fretting Wear ◽  
Steam Generators ◽  
Flow Induced Vibration ◽  
Support Materials ◽  
Mild Wear ◽  
Inconel 690

Tubes in nuclear steam generators are held up by supports because the tubes are long and slender. Fluid flows of high-pressure and high-temperature in the tubes cause oscillating motions between tubes and supports. This is called as FIV (flow induced vibration), which causes fretting wear in contact parts of tube-support. The fretting wear of tube-support can threaten the safety of nuclear power plant. Therefore, a research about the fretting wear characteristics of tube-support is required. This work is focused on fretting wear transitions from mild wear to severe wear of tube-support materials by various loads and relative displacements. The transition is defined on the basis of the changes in wear amount. To investigate the transition, the fretting wear tester was contrived to prevent the reduction of relative displacement between tube and support by increasing the load. The tube and support materials were Inconel 690 and 409 SS, respectively. The results show that the transition of tube-support wear is caused by the changes of the dominant wear mechanism depending on the applied load and the relative displacement.

Wear Characteristics of INCONEL 690 and INCONEL 600 in Elevated Temperature

2005 ◽  
Vol 297-300 ◽  
pp. 1424-1429 ◽  
Author(s):  
Sung Hoon Jeong ◽  
Young Ze Lee
Keyword(s):  
Wear Mechanisms ◽  
Nuclear Power ◽  
Power Plants ◽  
Elevated Temperatures ◽  
Fretting Wear ◽  
Wear Characteristics ◽  
Inconel 600 ◽  
Wear Life ◽  
Inconel 690 ◽  
C 50

In this paper, the fretting wear characteristics of INCONEL 690 (I-690) and INCONEL 600 (I-600) was evaluated to verify the wear mechanism and the wear life. Because of the excellent corrosion-resistance of nickel-based alloy, those materials are used for steam generator tube in nuclear power plants. Sometimes the tubes are damaged due to small amplitude vibration, so called fretting wear. To verify the fretting wear mechanisms the wear experiment was carried with the crossed-cylinder wear tester, which used a cam to oscillate the specimen. The test was carried out at loads of 40N and 90N in elevated temperatures of water. The temperatures of water were 20°C, 50°C and 80°C. The increase of water temperature causes the oxidation of the contact area to be delayed, and the amount of wear on oxide layer to be reduced. The main wear mechanisms of fretting were abrasive wear and oxidation wear.

308 Impact-Fretting Wear Properties of Carbon Steels in High Temperature Pure Water

2013 ◽  
Vol 2013.49 (0) ◽  
pp. 85-86
Author(s):  
Akito OYAKAWA ◽  
Akira IWABUCHI ◽  
Michimasa UCHIDATE ◽  
Hitoshi YASHIRO ◽  
Yoshiki SATO
Keyword(s):  
High Temperature ◽  
Pure Water ◽  
Carbon Steels ◽  
Fretting Wear ◽  
Wear Properties

An experimental study on the fretting wear behavior of Inconel 600 and 690 in pure water

Wear ◽  
2021 ◽  
Vol 486-487 ◽  
pp. 203995
Author(s):  
P. Zhang ◽  
J. Li ◽  
H.L. Yu ◽  
X.H. Tu ◽  
W. Li
Keyword(s):  
Experimental Study ◽  
Wear Behavior ◽  
Pure Water ◽  
Fretting Wear ◽  
Inconel 600

THREE DIMENSIONAL FINITE ELEMENT SIMULATION OF THE FRETTING WEAR PROBLEMS

2006 ◽  
Vol 20 (25n27) ◽  
pp. 3890-3895 ◽  
Author(s):  
CHOON YEOL LEE ◽  
JOON WOO BAE ◽  
BYUNG SUN CHOI ◽  
YOUNG SUCK CHAI
Keyword(s):  
Finite Element Analysis ◽  
Finite Element ◽  
Three Dimensional ◽  
Fretting Wear ◽  
Symmetric Model ◽  
Two Dimensional ◽  
Element Analysis ◽  
Inconel 690 ◽  
Dimensional Finite Element ◽  
Three Dimensional Finite Element

The structural integrity of steam generators in nuclear power plants is very much dependent upon the fretting wear characteristics of Inconel 690 U-tubes. In this study, a finite element analysis was used to investigate fretting wear on the secondary side of the steam generator, which arises from flow-induced vibrations (FIV) between the U-tubes and supports or foreign objects. Two-dimensional and three-dimensional finite element analyses were adopted to investigate the fretting wear problems. The purpose of the two-dimensional analysis, which simulated the contact between a punch and a plate, was to demonstrate the validity of using finite element analysis to analyze fretting wear problems. This was achieved by controlling the value of the wear constant and the number of cycles. The two-dimensional solutions obtained from this study were in good agreement with previous results reported by Strömberg. In the three-dimensional finite element analysis, a quarterly symmetric model was used to simulate tubes contacting at right angles. The results of the analyses showed donut-shaped wear along the contacting boundary, which is a typical feature of fretting wear.

Research on the Distribution of Subsurface Damage Layer on SiC Substrate After Double-Side Lapping

2015 ◽  
Vol 14 (01) ◽  
pp. 1-10 ◽  
Author(s):  
Hai Zhou ◽  
Xiaoming Xu ◽  
Xiang Gao ◽  
Yuan Zhang
Keyword(s):  
Silicon Carbide ◽  
Surface Damage ◽  
Damage Mechanism ◽  
Processing Parameters ◽  
Subsurface Damage ◽  
Shape Measurement ◽  
Theoretic Model ◽  
Damage Layer ◽  
Silicon Carbide Substrate ◽  
Measurement Laser

In this paper, the surface damage mechanism of silicon carbide lapping process was studied. A theoretic model between the depth of subsurface damage and surface scratch of silicon carbide substrate double-side lapping has been built. An experiment of two-sided lapping combining VK-X100/X200 shape measurement laser microscopy system with HF mild chemical etching experiment on SiC substrate was processed to obtain the distribution of surface scratch and subsurface damage layer with depth. The study shows that the thickness of subsurface damage layer decreases as the depth increases, which centrally distributes in the depth of 0–15.6 μm from outer fragmentation and scratch damage layer, which accounted for about 98.6%. The result can help us to optimize processing parameters of silicon carbide substrate double-side lapping to control the depth of subsurface damage layer.

Sign in / Sign up

Export Citation Format

Share Document