1. Introduction
Current nuclear reactors have progressed to the fourth generation [1]. Sodium-cooled fast reactors are the focus of research on fourth-generation nuclear reactors [2]. These reactors use sodium metal as a coolant. Sodium is characterized as having a violent chemical reaction with water, water vapor, or oxygen [3]. When the tube of a heat exchanger leaks or breaks, a severe exothermic reaction occurs between sodium and water. This sodium–water reaction event is generally considered in the design of sodium-cooled fast reactors [4]. Therefore, studying the damage mechanism of heat transfer tubes is necessary. The literature indicates that fretting wear due to the flow-induced vibration (FIV) [5] between the structure and fluid in a heat exchanger is one of the damage forms of heat transfer tubes. Fretting wear is also described as a type of wear phenomenon that occurs on two contact surfaces subject to small amplitude oscillations [6].
Current studies on heat transfer tubes are mainly focused on the second generation of pressurized water reactors. The 690 alloy was widely used in heat transfer tubes in the second generation of pressurized water reactors due to its excellent intergranular corrosion and intergranular stress corrosion cracking properties [7]. In recent years, fretting wear research on Inconel 690 alloys has covered contact forms [8,9], environment and temperatures [10,11,12], loads, and displacements [13,14,15,16]. In addition, a number of studies have focused on the effects of grain size and hardness [17], carbide size, and spacing [18] on the fretting wear properties of Inconel 690. Mi et al. [19] found that, at 90 °C, the wear mechanisms are delamination and abrasive wear. At 200 °C and 285 °C, the wear mechanisms are delamination, adhesion, and abrasive wear. Lu et al. [20] characterized the wear surface and subsurface layer of Inconel 690 alloys and found five layers, namely, an oxide layer, mixed layer, tribological transformed structure (TTS) layer, plastic deformation layer, and base material.
The low-alloy ferritic bainite steel, 2.25Cr-1Mo steel, is a candidate material for the high-temperature heat transfer tubes of fourth-generation nuclear reactors [21]. For the past 30 years, scholars have carried out extensive studies on the microstructure [22], high-temperature creep [23,24], welding [25,26], and radiation resistance [27] of 2.25Cr-1Mo steel. However, studies on the wear properties of 2.25Cr-1Mo steel are relatively few. Pattnaik et al. [28] systematically studied the erosion and wear of 2.25Cr-1Mo steel. Their results showed that, under normal conditions, impact speed is an important factor that causes maximum wear. Under thermal aging conditions, erodent size is the most important factor affecting wear. A similar study was carried out by Sahoo et al. [29]. The results indicated that the Larson–Miller parameter exerts a great static influence of 46.33%, impingement angle has an influence of 42.51%, impact velocity has an influence of 7.47%, and the erodent size has an influence of 1.13% on the solid particle erosion behavior of this alloy.
Therefore, the current work mainly studies the tangential fretting wear properties of 2.25Cr-1Mo steel at varied temperatures. This study is significant in the evaluation of the wear performance of 2.25Cr-1Mo steel. 2. Experimental Procedure 2.1. Materials and Specimens
In this work, 2.25Cr-1Mo steel was investigated under dry sliding. The material of its friction pair was a Gr5C12 alloy rod, which was used as the tube support plate material in the heat exchangers. All test materials were supported by the Central Research Academy of Dongfang Electric Corporation (Chengdu, China). The chemical composition (wt.%) is listed in Table 1. The original tube was cut with an electric spark wire. The length of the 2.25Cr-1Mo steel tube specimen was 30.0 mm, and the outer and inner diameters were 16.0 and 11.0 mm, respectively. The original plate was cut into strips with an electric spark wire, then machined into rods (with a diameter of 10.7 mm). Finally, the Gr5C12 rod was cut to a specimen with a length of 20.0 mm. All samples were sanded mechanically, and polished by a polishing machine. So, the surface roughness of all tested materials was 0.4 μm. The samples were ultrasonically cleaned with banana oil, deionized water, and absolute ethanol and dried with hot compressed air before the tests.
2.2. Tribological Testing and Analysis
All the tests were performed using self-developed high-temperature tangential fretting wear equipment, which was mainly composed of a voice coil motor, frame and weight lifting platform, control and measurement systems, data acquisition systems, and other spare parts. The device was appropriately designed and easy to use. A simple schematic diagram is drawn in Figure 1a. The control and data acquisition programs were installed on a computer. After clamping the sample, the computer was used to input the test parameters (amplitude and frequency). The general procedure of the test was as follows. In the first step, the lower sample (8) and the heating rod (7) were fixed and inserted into the lower fixture (6). The lower fixture (6) and heat insulation plate (4) were fixed onto the guide rail (3) by bolts. In the second step, the upper sample (9) was fixed on the upper fixture (10), and the upper fixture (10) and heat insulation plate (11) were fixed onto the equipment together. In the third step, the temperature control box (16) was used to control the heating rod (7) for heat generation until the temperature sensor (5) returned a temperature that reached a preset value. In the fourth step, the spinner handle (15) was used to drop the horizontal position of the upper sample (9) until it simply made contact with the lower sample (8). Then, a weight (13) was used to press the upper sample (9) against the lower sample (8). In the fifth step, the voice coil motor (1) was controlled by the computer to start reciprocation (at x direction). The grating ruler (2) and force sensor (12) monitored the displacements and friction signal during the test in real time and cyclically fed them back to the computer. The image of the actual equipment is shown in Figure 1b and the schematic diagram of motion is shown in Figure 1c.
Table 2 shows the specific experimental parameters. Given the influence of a high temperature environment on the fretting wear properties of 2.25Cr-1Mo steel, four temperature gradients (room temperature (RT), 80 °C, 225 °C, and 450 °C) were set. Two types of normal loads (10 N, 20 N) (close to actual working conditions), displacement amplitudes (50 μm, 100 μm), and a frequency of 5 Hz and 104 cycles were selected. Tests 1–3 (20 N-50 μm, 10 N-50 μm, 10 N-100 μm) were designed at all temperatures, and each group of experiments was repeated three times. After the tests, the three sets of repeated test data were averaged and the corresponding error bar was calculated (using the standard deviation). The surface morphology of the worn scar was observed using a super depth field microscope (VHX-7000, KEYENCE, Osaka, Japan). A white light interference microscope uses the principle of interference to measure the optical path difference to determine the relevant physical quantities. Therefore, it can be used to determine the three-dimensional shape of the wear scar, and then the wear area, depth, and volume can be obtained by the analysis software Vision. The detailed morphology and chemical reaction of the worn scars were studied by scanning electron microscopy (SEM, JSM 7800F, JEOL, Tokyo, Japan) and energy dispersive X-ray spectroscopy (EDX, Aztec X-Max 80, Oxford instrument, Abingdon, UK), respectively. In addition, electron probe micro-analyzer (EPMA, JXA-8230, JEOL, Tokyo, Japan) spectroscopy was conducted to examine the main elements of the cross section of the worn scar.
3. Results and Discussion 3.1. Friction Coefficient
The coefficient of friction is the result of dividing the average friction force (using 10% of the collected data near the peak friction force) by the normal load. The evolution of the coefficient of friction as a function of cycle numbers is shown in Figure 2. In general, as the number of cycles increases, the COF can be approximately divided into five stages (initial, ascending, peak, descending, and steady stages) [4]. The initial and ascending stages generally involve the removal of the oxidative layer of the material [30]. At 225 °C and 450 °C, the COF reaches the steady stages only after a few tens of cycles. This behavior indicates that the initial oxidative layer of 2.25Cr-1Mo steel is easily removed at high temperatures. The generation and removal of abrasive debris also reach a dynamic balance faster in high temperatures than in low temperatures. In nearly all the tests, as the temperature increases, the average COF increases first and then decreases (Figure 2d). This result is consistent with Mi’s research on 690 tubes in high-temperature water [19]. The maximum average COF in the stable stage is 0.500 at 80 °C, and the minimum COF is 0.451 in the stable stage at 450 °C (Figure 2d). The COF also increases with the increase in load and amplitude [16,19].
The curve of friction force and displacement (Ft-D) between contact surfaces is the most basic and important indicator of tangential fretting wear [31]. The fretting maps of the three groups of tests after 104 cycles are shown in Figure 3. In general, temperature exerts some influence on the fretting model, but greater influence comes from the normal load and sliding displacement [16,32]. At 20 N, the fretting map is linear at room temperature or a high temperature, indicating that the fretting model is a partial slip condition. However, at 10 N, the fretting map is basically a parallelogram, implying that the fretting model is a gross slip condition. As the amplitude increases, the gross slip becomes pronounced. As shown in Figure 3c,d, the fretting maps at 225 °C and 450 °C, shown with a red line, show an oval shape. This condition indicates that the slip regime becomes a mixed regime with the increase in temperature. Meanwhile, the dissipated energy within Figure 3a–d was calculated (Figure 3e). For a single cycle, the dissipated energy is the area within a hysteresis loop between tangential force and relative slip (Ft–D plot) [33]. The results show that the dissipated energy has a negative correlation with the load and a positive correlation with the amplitude [34]. However, there is no clear relationship between the temperature and dissipated energy.
3.2. Wear Mechanisms
The fretting wear property of the 2.25Cr-1Mo steel tube was analyzed, and the worn scars were observed, as shown in Figure 4. When the temperature increases, the surface color of the sample changes first. Especially at 225 °C and 450 °C, the color of the sample surface is clearly different. Meanwhile, the black oxide on the surface of the worn scar increases gradually with the temperature, thereby indicating that the severe oxidation of the heat transfer tubes occurs at a high temperature. The edge of the worn scar is more severely worn than the middle of the worn scar (Figure 4).
For further study of the worn scars, Figure 5 presents the sectional profiles and 3D topography of the worn scars. In the direction perpendicular to the sliding direction (y direction), the profile of the black line is high in the middle and low on both sides, while the profile of the red line is high on both sides and low in the middle [35]. In the direction parallel to the sliding direction (x direction), the profile of the red line is significantly raised at both ends, while the profile of the black line is relatively smooth (Figure 5a). Meanwhile, the deeper material loss, material transfer, or plastic deformation increases with temperature (Figure 5a,c,e), indicating that high temperatures (≥225 °C) may cause deeper material wear.
At 10 N, the edge area of the worn scars is significantly high, especially in the edge area parallel to the sliding direction (Figure 5b). However, at 20 N, the edge area of the worn scar is relatively flat, and the middle area is high. These features also prove that gross slip occurs at 10 N, and partial slip occurs at 20 N. Moreover, the existence of furrows can be clearly seen in Figure 5b,d,f, which are the traces left after the material is peeled out of the friction interface [19]. The red mountain peak increases with the temperature, thereby indicating that high temperatures (≥225 °C) may cause severe material transfer or plastic deformation.
The worn scars were quantitatively studied further. Figure 6 shows the results of wear volume and wear area. When the temperature increases, the wear volume first increases and then decreases. The maximum wear volume occurs at 80 °C. By contrast, the wear volume is small at 225 °C and 450 °C and presents a minimal difference under the same test parameters. Thus, deeper material wear does not mean maximum material removal. At the same temperature, the wear volume increases with displacement and decreases with an increase in load. Thus, wear volume is greatly affected by temperature, normal load, and sliding displacements. Meanwhile, the wear area increases first and then decreases with an increase in temperature, but the change is not obvious. The maximum wear area for tests 1 and 2 occurs at 225 °C, whereas the maximum wear area for test 3 appears at 80 °C. Temperature exerts a slight effect on wear area, and load and amplitude are the main factors affecting wear area.
Figure 7 shows the results of the average wear depth and wear coefficient. The average wear depth is obtained by dividing the wear volume and wear area. As shown in Figure 7a, all the average wear depths of the three groups of tests are larger at room temperature and 80 °C than at 225 °C and 450 °C. In other words, 2.25Cr-1Mo steel has localized deep wear at high temperatures, but the average depth of the entire wear scar is lower than that at normal temperatures. In combination with the wear volume in Figure 6, the material shows reduced spalling at 225 °C and 450 °C, thereby indicating that high temperatures may protect materials. This result may be attributed to the antifriction nature and stabilized high lubrication properties of the oxidative layer and the effect of plastic deformation [20,36].
The formula for calculating the wear coefficient has been described in the following form [37]:
dD(x)dN=K×q(x)×(4δ)
where D(x) and q(x) are the wear depth and contact shear force, respectively, N is the number of fretting cycles,δis the displacement amplitude, and K is termed as a wear coefficient with the unit of Pa−1. If we focus on the average depth, Equation (1) is written as
dDavedN=K×qave×(4δ)
whereDaveis the average wear depth andqave is the average shear traction (friction force). The wear coefficient is inversely proportional to the normal load and sliding displacement. The statistical results of the wear coefficient in Figure 7b support this result. The wear coefficients of tests 2 and 3 first increase and then decrease with an increase in temperature. The wear coefficient of test 1 decreases with increases in temperature. This phenomenon shows that temperature has less influence on the wear coefficient than normal load and sliding displacement. The value of the wear coefficient reflects the degree of wear in a single cycle. Therefore, each fretting cycle of test 2 achieves the greatest wear to the 2.25Cr-1Mo steel tubes, and the wear of each fretting cycle of test 3 is minimal.
A typical SEM image of the worn scars was observed to study the wear mechanism of 2.25Cr-1Mo steel. As shown in Figure 8, wear debris hardly accumulate but scatter in the concave surface of the friction interface or the edge of the worn scars at RT (Figure 8a). As the temperature increases to 80 °C, the surface of the scratched area clearly shows ploughing due to abrasive wear (Figure 8b). In addition, the friction interface is relatively smooth and shows a wear debris accumulation area at higher temperatures (Figure 8c,d). Figure 8e shows the element content of points 1–8 within Figure 8a–d. The oxygen content of the point in the wear scar increases with the temperature increase. At 450 °C, the presence of oxygen is also detected on the substrate other than the wear scar, which indicates that the high temperature oxidized the material before the test. So, at 10 N, scratching, ploughing, abrasive, and oxidation wear are the main wear mechanisms of the 2.25Cr-1Mo steel tube. As shown in Figure 9, wear debris tend to accumulate at 20 N. At RT and 80 °C, the friction interface displays an obvious delamination area (Figure 9a,b). As the temperature increases to 225 °C and 450 °C, the surface of the scratched area clearly shows spalling and a wear debris accumulation area (Figure 9c,d). Figure 9e shows the element content of points 1–8 within Figure 9a–d. The oxygen content of the point in the wear scar also increases with the temperature increase. Meanwhile, at 450 °C, the presence of oxygen is also detected on the substrate other than the wear scar. This confirms the surface color change in Figure 4. So, at 20 N, spalling, delamination, adhesive, and oxidation wear are the main mechanisms of wear of the 2.25Cr-1Mo steel tube. Besides, in summary, as the temperature increases, the wear mechanism gradually changes from abrasive wear to adhesive wear.
The amounts of oxygen, chromium, molybdenum, and iron on the wear surface under four test conditions were measured by EDX (the accelerating voltage for EDX is 20 kv). The results are shown in Figure 10. The oxygen content is relatively high on the entire surface of the worn scar, and the contents of the other elements are reduced (Figure 10a,b). As mentioned previously, 10 N causes abrasive wear and covers the entire friction interface. As shown in Figure 10c,d, the oxygen content increases and decreases intermittently, and the other elements decrease and increase correspondingly. Evidently, 20 N causes the middle of the worn scar to stick and the edge of the worn scar to be oxidized. The oxygen content on the surface of the substrate that does not penetrate the worn scar at 450 °C is higher than that at 80 °C. Hence, the high temperature promoted the oxidation of 2.25Cr-1Mo steel before the test in this work. Meanwhile, the change in the amounts of chromium, molybdenum, and iron with oxygen at 450 °C is more obvious than that at 80 °C.
The cross section of a sample from test 2 at 450 °C was selected. The sample was cut with an electric spark wire, sanded with sandpaper, and then finally polished with a polishing paste. Section A-B is shown in Figure 11b. Delamination cracks form within the TTS (Figure 11c,f) [38]. Subsurface cracks are caused by surface fatigue effects, and they eventually connect to surface cracks, resulting in spalling and material removal. Meanwhile, the high hardness and refined grains of the TTS layer increase the strength of the surface [39] and may increase the wear resistance of 2.25Cr-1Mo steel.
Figure 12 shows the microstructure and elemental distribution of the portion cross section in Figure 11. Significant stratification morphologies are labeled as A–C. The amounts Cr, Mo, Fe, Mn, and S gradually decrease from the substrate to the oxide layer. In fact, the thickness of the oxide layer is only a few microns and is thus difficult to measure. By contrast, the TTS layer is clearly visible and contains a small amount of oxygen (almost zero) [40] of the same order of the substrate [38].
The wear mechanisms in air can be described by schematic diagrams, as shown in Figure 13. At RT, large wear debris are produced which result in serious abrasive wear and large wear volume. Meanwhile, abrasive debris act as self-lubricating agents [41], resulting in a small COF. At 80 °C, the wear mechanism is mainly the synergy of abrasive wear and adhesive wear, resulting in a larger wear volume and a higher COF. At 225 °C and 450 °C, adhesive wear gradually gains an advantage, resulting in a slight wear. Meanwhile, adhesive wear is influenced by temperature, as increasing temperature led to shorter sliding distances until the onset of severe adhesive wear, distinguished as an increase in the COF [42]. However, the oxide layer that is constantly generated at higher temperatures has the characteristics of an antifriction nature and stabilized high lubrication properties [20]. So, the COF at 450 °C is relatively small. In summary, elevated temperatures will help adhesive wear to defeat abrasive wear, and make the 2.25Cr-1Mo steel show more excellent wear resistance.
4. Conclusions The fretting wear behavior of a 2.25Cr-1Mo heat transfer tube against a Gr5C12 alloy rod with 104 cycles at varied temperatures (including two kinds of normal loads and displacement amplitudes) was studied. There are some other test parameters (such as contact form, tube diameter, test frequency, etc.) that may also affect the wear behavior of the 2.25Cr-1Mo heat transfer tube. This may be studied in the future. On the basis of the abovementioned results, the fretting wear properties of the 2.25Cr-1Mo steel heat transfer tube are described as follows:
(a) Wear volume and COF first increase and then decrease with an increase in temperature. The maximum wear volume and COF occur at 80 °C, whereas the minimum occurs at 450 °C.
(b) Wear mechanisms depend modestly on temperature and largely on normal load. As temperature increases, the wear mechanism gradually changes from abrasive wear to adhesive wear. Scratching, ploughing, abrasive, and oxidation wear are the main wear mechanisms in gross slip conditions at 10 N, whereas spalling, delamination, adhesive, and oxidation wear occur in partial slip conditions at 20 N.
(c) High temperatures (≥225 °C) may improve the wear resistance of 2.25Cr-1Mo steel due to the antifriction nature of the oxidative layer, the high hardness and refined grains of the TTS layer, and extensive material transfer and plastic deformation. This provides data support for the practical engineering application of 2.25Cr-1Mo steel at elevated temperatures.
Enlarge this image.Figure 1. Test equipment (a,b): (1) voice coil motor; (2) grating ruler; (3) guide rail; (4), (11) heat insulation plate; (5) temperature sensor; (6) lower fixture; (7) heating rod; (8) lower sample; (9) upper sample; (10) upper fixture; (12) force sensor; (13) weights; (14) envelope; (15) spinner handle; (16) temperature control box, and schematic diagram of motion (c).
Enlarge this image.Figure 3. Ft-D curves (a-d) and dissipated energy (e) with varied temperatures, cycles = 104.
Enlarge this image.Figure 4. Super depth field micrographs of worn scars at varied temperatures: F = 20 N, D = 50 μm.
Enlarge this image.Figure 5. Sectional profiles and 3D topography of worn scars under different normal loads, D = 50 μm.
Enlarge this image.Figure 10. EDX analysis of worn scars, D = 50 μm: (a), (b) F = 10 N; (c), (d) F = 20 N.
Enlarge this image.Figure 11. Morphologies of the cross section of a worn scar: T = 450 °C; F = 10 N; D = 50 μm.
Enlarge this image.Figure 12. Elemental distribution of the cross section of a worn scar: T = 450 °C; F = 10 N; D = 50 μm.
| Materials | Element | |||||||
|---|---|---|---|---|---|---|---|---|
| C | Mn | P | S | Si | Cr | Mo | Fe | |
| 2.25Cr-1Mo | 0.11 | 0.31 | 0.007 | 0.003 | 0.14 | 2.42 | 1.05 | bal |
| Gr5C12 | ≤0.15 | 0.30–0.60 | ≤0.035 | ≤0.035 | ≤0.50 | 4.00–6.00 | 0.45–0.65 | bal |
| Item | Value |
|---|---|
| Tube materials | 2.25Cr-1Mo |
| Tube hardness | 177.73 HV |
| Tube Young’s modulus | 194.73 Gpa |
| Rod materials | Gr5C12 |
| Rod hardness | 177.43 HV |
| Rod Young’s modulus | 179.32 Gpa |
| Temperature | RT, 80 °C, 225 °C, 450 °C |
| Load | 10 N, 20 N |
| Amplitude | 50 μm, 100 μm |
| Frequency | 5 Hz |
| Number of cycles | 104 cycles |
Author Contributions
Conceptualization, L.-W.W.; Data curation, L.-Y.Y.; Formal analysis, L.-Y.Y. and R.T.; Supervision, Z.-B.C.; Writing-original draft, X.-D.C. and R.T.; Writing-review and editing, X.-D.C. All authors have read and agreed to the published version of the manuscript.
Funding
This research received no external funding.
Acknowledgments
The authors would like to acknowledge the valuable support from the Central Research Academy of Dongfang Electric Corporation for the test materials.
Conflicts of Interest
The authors declare no conflict of interest.
1. Lake, J.A. The fourth generation of nuclear power. Prog. Nucl. Energy 2002, 40, 301-307.
2. Ichimiya, M. A next generation sodium-cooled fast reactor concept and its R&D program. Nucl. Eng. Technol. 2007, 39, 171-186.
3. Ahn, S.J.; Ha, K.-S.; Chang, W.-P.; Kang, S.H.; Lee, K.L.; Choi, C.-W.; Lee, S.W.; Yoo, J.; Jeong, J.-H.; Jeong, T. Evaluation of a sodium-water reaction event caused by steam generator tubes break in the prototype generation IV sodium-cooled fast reactor. Nucl. Eng. Technol. 2016, 48, 952-964.
4. Aoto, K.; Uto, N.; Sakamoto, Y.; Ito, T.; Toda, M.; Kotake, S. Design study and R&D progress on Japan sodium-cooled fast reactor. J. Nucl. Sci. Technol. 2011, 48, 463-471.
5. Young, B.; Gao, X.; Srivatsan, T.S.; King, P.J. The response of alloy 690 tubing in a pressurized water reactor environment. Mater. Des. 2007, 28, 373-379.
6. Cai, Z.-B.; Li, Z.-Y.; Yin, M.-G.; Zhu, M.-H.; Zhou, Z.-R. A review of fretting study on nuclear power equipment. Tribol. Int. 2020, 144, 106095.
7. Zhao, Y.; Choi, I.-C.; Kim, Y.-J.; Jang, J.-I. On the nanomechanical characteristics of thermally-treated alloy 690: Grain boundaries versus grain interior. J. Alloys Compd. 2014, 582, 141-145.
8. Jeong, S.-H.; Cho, C.-W.; Lee, Y.-Z. Friction and wear of Inconel 690 for steam generator tube in elevated temperature water under fretting condition. Tribol. Int. 2005, 38, 283-288.
9. Yin, M.-G.; Cai, Z.-B.; Zhang, Z.-X.; Yue, W. Effect of ultrasonic surface rolling process on impact-sliding wear behavior of the 690 alloy. Tribol. Int. 2019, 147, 105600.
10. Mi, X.; Xie, H.; Tang, P.; Cai, Z.-B.; Peng, J.-F.; Zhu, M.-H. Effect of environmental condition on the chemical behavior of 690 alloy during fretting wear. Tribol. Int. 2020, 146, 106202.
11. Wang, Z.; Lu, Y.; Li, J.; Shoji, T. Effect of pH value on the fretting wear behavior of Inconel 690 alloy. Tribol. Int. 2016, 95, 162-169.
12. Lai, P.; Gao, X.; Tang, L.; Guo, X.; Zhang, L. Effect of temperature on fretting wear behavior and mechanism of alloy 690 in water. Nucl. Eng. Des. 2018, 327, 51-60.
13. Xin, L.; Yang, B.; Wang, Z.; Li, J.; Lu, Y.; Shoji, T. Effect of normal force on fretting wear behavior and mechanism of Alloy 690TT in high temperature water. Wear 2016, 368, 210-218.
14. Guo, X.; Lai, P.; Tang, L.; Wang, J.; Zhang, L. Effects of sliding amplitude and normal load on the fretting wear behavior of alloy 690 tube exposed to high temperature water. Tribol. Int. 2017, 116, 155-163.
15. Ming, H.; Liu, X.; Zhang, Z.; Wang, J.; Han, E.-H. Effect of normal force on the fretting wear behavior of Inconel 690 TT against 304 stainless steel in simulated secondary water of pressurized water reactor. Tribol. Int. 2018, 126, 133-143.
16. Zhang, X.-Y.; Cai, Z.-B.; Peng, J.-F.; Liu, J.-H.; Zhu, M.-H.; Du, R.; Yuan, X.-L.; Ren, P.-D. Experimental study of the fretting wear behavior of Inconel 690 alloy under alternating load conditions. Proc. Inst. Mech. Eng. Part J J. Eng. Tribol. 2018, 232, 1343-1351.
17. Li, J.; Lu, Y.; Zhang, H.; Xin, L. Effect of grain size and hardness on fretting wear behavior of Inconel 600 alloys. Tribol. Int. 2015, 81, 215-222.
18. Yun, J.Y.; Shin, G.S.; Kim, D.I.; Lee, H.S.; Kang, W.S.; Kim, S.J. Effect of carbide size and spacing on the fretting wear behavior of Inconel 690 SG tube mated with SUS 409. Wear 2015, 338, 252-257.
19. Mi, X.; Wang, W.; Xiong, X.; Qian, H.; Tang, L.; Xie, Y.; Peng, J.; Cai, Z.; Zhu, M.-H. Investigation of fretting wear behavior of Inconel 690 alloy in tube/plate contact configuration. Wear 2015, 328, 582-590.
20. Xin, L.; Yang, B.; Wang, Z.; Li, J.; Lu, Y.; Shoji, T. Microstructural evolution of subsurface on Inconel 690TT alloy subjected to fretting wear at elevated temperature. Mater. Des. 2016, 104, 152-161.
21. Klueh, R.; Nelson, A.T. Ferritic/martensitic steels for next-generation reactors. J. Nucl. Mater. 2007, 371, 37-52.
22. Deng, D.; Murakawa, H. Finite element analysis of temperature field, microstructure and residual stress in multi-pass butt-welded 2.25 Cr-1Mo steel pipes. Comput. Mater. Sci. 2008, 43, 681-695.
23. Whittaker, M.; Wilshire, B. Long term creep life prediction for Grade 22 (2 25Cr-1Mo) steels. Mater. Sci. Technol. 2011, 27, 642-647.
24. Muránsky, O.; Zhu, H.; Lim, S.-L.; Short, K.; Cairney, J.; Drew, M. On the evolution of mechanical properties and microstructure of ferritic-bainitic (FB) 2.25 Cr-1Mo (Grade 22) steel during high-temperature creep. Materialia 2020, 9, 100513.
25. Ren, S.; Li, S.; Wang, Y.; Deng, D.; Ma, N. Finite element analysis of residual stress in 2.25 Cr-1Mo steel pipe during welding and heat treatment process. J. Manuf. Process. 2019, 47, 110-118.
26. Elrefaey, A.; Javadi, Y.; Francis, J.A.; Callaghan, M.D.; Leonard, A.J. Evolution of microstructure and toughness in 2.25 Cr-1Mo steel welds. Int. J. Press. Vessels Pip. 2018, 165, 20-28.
27. Mao, X.; Takahashi, H.; Kodaira, T. Supersmall punch test to estimate fracture toughness Jic and its application to radiation embrittlement of 2.25 Cr-1Mo steel. Mater. Sci. Eng. A 1992, 150, 231-236.
28. Pattnaik, A.B. Erosive wear analysis of normalised and thermally aged 2.25 Cr-1Mo steel using Taguchi experimental design. Indian J. Eng. Mater. Sci. 2014, 21, 379-386.
29. Sahoo, R.; Jha, B.; Sahoo, T.; Mantry, S. Effect of microstructural degradation on solid particle erosion behavior of 2.25 Cr-1Mo steel. Tribol. Trans. 2014, 57, 679-689.
30. Li, Z.-Y.; Yang, W.-J.; Wu, Y.-P.; Wu, S.-B.; Cai, Z.-B. Role of humidity in reducing the friction of graphene layers on textured surfaces. Appl. Surf. Sci. 2017, 403, 362-370.
31. Zhu, M.H.; Zhou, Z.R. Composite fretting wear of aluminum alloy. Key Eng. Mater. 2007, 353, 868-873.
32. Yun, J.Y.; Park, M.C.; Shin, G.S.; Heo, J.H.; Kim, D.I.; Kim, S.J. Effects of amplitude and frequency on the wear mode change of Inconel 690 SG tube mated with SUS 409. Wear 2014, 313, 83-88.
33. Magaziner, R.; Jain, V.; Mall, S. Investigation into wear of Ti-6Al-4V under reciprocating sliding conditions. Wear 2009, 267, 368-373.
34. Marc, E.; Fouvry, S.; Phalippou, C.; Maitournam, H. Fretting wear response of a nitrided 316L SS/304L SS interface: Effect of lithium/bore liquid environment. Surf. Coat. Technol. 2016, 308, 226-235.
35. Zhang, X.-Y.; Liu, J.-H.; Cai, Z.-B.; Peng, J.-F.; Zhu, M.-H.; Ren, P.-D. Experimental study of the fretting wear behavior of Incoloy 800 alloy at high temperature. Tribol. Trans. 2017, 60, 1110-1119.
36. Mi, X.; Cai, Z.; Xiong, X.; Qian, H.; Tang, L.; Xie, Y.; Peng, J.; Zhu, M.-H. Investigation on fretting wear behavior of 690 alloy in water under various temperatures. Tribol. Int. 2016, 100, 400-409.
37. Kim, H.-K.; Lee, Y.-H. Wear depth model for thin tubes with supports. Wear 2007, 263, 532-541.
38. Sauger, E.; Fouvry, S.; Ponsonnet, L.; Kapsa, P.; Martin, J.; Vincent, L. Tribologically transformed structure in fretting. Wear 2000, 245, 39-52.
39. Fangyuan, Z.; Chunzheng, D.; Wei, S.; Kang, J. Influence of White Layer and Residual Stress Induced by Hard Cutting on Wear Resistance During Sliding Friction. J. Mater. Eng. Perform. 2019, 28, 7649-7662.
40. Xin, L.; Wang, Z.; Li, J.; Lu, Y.; Shoji, T. Microstructural characterization of subsurface caused by fretting wear of Inconel 690TT alloy. Mater. Charact. 2016, 115, 32-38.
41. Ghasemi, R.; Elmquist, L.; Ghassemali, E.; Salomonsson, K.; Jarfors, A.E. Abrasion resistance of lamellar graphite iron: Interaction between microstructure and abrasive particles. Tribol. Int. 2018, 120, 465-475.
42. Gåård, A.; Hallbäck, N.; Krakhmalev, P.; Bergström, J. Temperature effects on adhesive wear in dry sliding contacts. Wear 2010, 268, 968-975.
Xu-Dong Chen1, Li-Wen Wang2,*, Ling-Yun Yang1, Rui Tang1 and Zhen-Bing Cai1,*
1Tribology Research Institute, Key Lab of Advanced Technologies of Materials, Ministry of Education, South West Jiaotong University, Chengdu 610031, China
2Central Research Academy, Dongfang Electric Corporation, Chengdu 611731, China
*Authors to whom correspondence should be addressed.
© 2020. This work is licensed under http://creativecommons.org/licenses/by/3.0/ (the “License”). Notwithstanding the ProQuest Terms and Conditions, you may use this content in accordance with the terms of the License.
Details
