Fretting Wear Characteristics of INCONEL 690 and INCONEL 600 in Water Environment

2005 ◽  
pp. 1412-1417
Author(s):  
Sung Hoon Jeong ◽  
Chi Yong Park ◽  
Young Ze Lee
Keyword(s):  
Water Environment ◽  
Fretting Wear ◽  
Wear Characteristics ◽  
Inconel 600 ◽  
Inconel 690

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.

Fretting Wear Characteristics of INCONEL 690 and INCONEL 600 in Water Environment

2005 ◽  
Vol 297-300 ◽  
pp. 1412-1417 ◽  
Author(s):  
Sung Hoon Jeong ◽  
Chi Yong Park ◽  
Young Ze Lee
Keyword(s):  
Nuclear Power ◽  
Water Environment ◽  
Fretting Wear ◽  
Wear Loss ◽  
Stick Slip ◽  
Inconel 600 ◽  
Delamination Wear ◽  
Slip Regime ◽  
Inconel 690 ◽  
Steam Generator Tubes

Fretting is the oscillatory motion with very small amplitudes, which usually occurs between two solid surfaces in contact. Fretting wear is the removal of material from contacting surfaces through fretting action. Fretting wear of steam generator tubes in nuclear power plant becomes a serious problem in recent years. The materials for the tubes usually are INCONEL 690 (I-690) and INCONEL 600 (I-600). In this paper, fretting wear tests for I-690 and I-600 were performed under various applied loads in water at room temperature. Results showed that the fretting wear loss of I-690 and I-600 tubes was largely influenced by stick-slip. The fretting wear mechanisms were the abrasive wear in slip regime and the delamination wear in stick regime. Also, I-690 had somewhat better wear resistance than I-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.

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