Abstract
The service water environment of high temperature and high pressure was simulated for the steam generator heat transfer tube of pressurized water reactor. 690 TT alloy tube and 405 SS plate were used to form the friction pair for impact slip dual-axis fretting corrosion experiments. The microstructure evolution of 690 TT alloy tube during dual-axis impact slip fretting corrosion was investigated. White light interferometer, scanning electron microscope, transmission electron microscope, and Raman spectrum were used to investigate the microstructure and abrasive products of the abraded surface and near-surface. Results indicate that within 1
Steam generator (SG) is a crucial component in pressurized water reactors, and the safe operation of SG heat transfer tubes is essential for the overall reactor performance. The research on the microstructure evolution of 690 TT heat transfer tubes during impact slip dual-axis fretting corrosion in high temperature and high pressure water environment is of great significance.
690 TT alloy, as an austenitic nickel-based alloy, is selected to manufacture SG heat transfer tubes due to its excellent resistance against stress corrosion cracking. However, the continuous small displacements, sliding, and collisions between the heat transfer tubes and support plates or anti-vibration strips may lead to thinning and fracture of the tube wall.
The physical and chemical factors, such as temperature, amplitude, frequency, dissolved oxygen and hydrogen concentrations, and pH valu
Therefore, in this research, the service environment was simulated and the effect of the number of cycles on fretting corrosion was discussed under high temperature and high pressure water environment. The microstructure evolution was investigated to analyze the damage mechanism and behavior of 690 TT alloy heat transfer tubes under these specific conditions. Besides, a predictive model was established to predict and accurately evaluate the wear degree. Particularly, this research analyzed the entry process of stable stage in the wear process. Studying the microstructure evolution is crucial for the development and accuracy of prediction model in the wear process. Thus, this research simulated the actual environment in the reactor and studied the microstructure evolution of 690 TT alloy tube during impact slip wear under high temperature and high pressure conditions, which is essential to understand the mechanism and improve the performance with service life of SG heat transfer tubes, ultimately contributing to the safe efficient operation of pressurized water reactors.
690 TT alloy is one of the most commonly used materials for the manufacture of heat transfer tubes in SGs, and the racks of heat transfer tubes are usually made of 405 SS material. Therefore, in the wear experiments, nuclear-grade commercial 690 TT alloy tubes and 405 SS plates were selected as wear pair. The chemical composition of 690 TT tube and 405 SS plate is provided in
Material | Ni | Cr | Fe | Mn | Ti | Al | C |
---|---|---|---|---|---|---|---|
690 TT | 59.3 | 29.8 | 9.3 | 0.2 | 0.3 | 0.4 | 0.01 |
405 SS | 0.3 | 13.1 | 85.3 | 0.7 | - | 0.1 | 0.056 |
The 690 TT wear samples was cut into the ones with length of 15 mm, and the surface of 405 SS plate was polished. The samples were then washed with anhydrous ethanol and dried.
As shown in

Fig.1 Schematic diagram of wear pair
This experiment was conducted in an autoclave to attain the high pressure conditions and a high-temperature sensor was used to ensure the high temperature conditions. The impact shaft and sliding shaft were driven by a servo motor, and a sealing ring was used at the connection between the shaft and the high pressure kettle to ensure the high pressure environment inside the autoclave.
Ammonia was used to adjust the pH value of the deionized water in the water tank to 10±0.05. Continuous bubbling of N2 was employed to deoxygenate the water and control the dissolved oxygen value as 10±0.05 μg/L.
The temperature of the autoclave was controlled as 285 °C, and the back pressure valve was adjusted to increase the pressure inside the kettle to 8.6 MPa. Once the conditions inside the autoclave satisfied the set ones, the sliding displacement of the wear test was set as ±150 μm.
Throughout the testing period, a normal force of 0–80 N was applied to the 690 TT alloy tube using a normal loading system in a sine wave manner. Simultaneously, the 405 SS plate underwent reciprocating motion controlled by the lateral driving system at the testing frequency of 30 Hz.

Fig.2 FIB sample preparation process: (a) spray coating protective layer; (b) rough cut; (c) extraction; (d) gradual thinning
As shown in

Fig.3 SEM images of initial grains in 690 TT alloy tube (a) and 405 SS plate (b)

Fig.4 EBSD images (a–b) and grain size distributions (c–d) of 690 TT alloy tube (a, c) and 405 SS plate (b, d)
The grain size of the 690 TT alloy tube ranges from 10 μm to 70 μm, whereas that of the 405 SS plate ranges from 5 μm to 110 μm. Ref.[
Due to the annealing treatment, the grain size distribution in the matrix of 690 TT alloy tube is uniform, and no significant difference can be observed in grain sizes between the sample surface and the matrix. Consequently, the influence of grain size on wear is barely changed with the increase in wear depth.

Fig.5 3D profiles of wear marks on surface of 690 TT alloy tube (a–c) and 405 SS plate (d–f) after different cycles: (a, d) 1
It can be observed that the contour of the wear marks in Fig.
Notably, visible protrusions of above 4 μm can be observed on the unworn surface on both sides of the wear mark. These protrusions may originate from the plastic deformation of the material in the center area of 690 TT tube due to abrasive wear or material transfer from the 405 SS plate.
Under the influence of adhesive wear, debris generated on the 405 SS plate adheres to the surface of 690 TT alloy tube. Subsequent squeezing motion causes the transferred material to move and accumulate along the sliding direction, resulting in protrusions on the surface. Material transfer occurs not only at the edge of the wear scar but also in the center wear area. The accumulation of material transfer leads to the elevation of the edge area of the wear scar, compared with other regions.

Fig.6 Wear volumes of 690 TT alloy tube after different cycles
Through the calculation of the average wear amount in samples after 5×1
Considering the wear volume, it is important to note that subsequent wear cannot be perceived as a repetition of the previous wear process. To determine whether the process from 5×1
Fig.

Fig.7 Wear depth profiles of 690 TT alloy tube (a) and 405 SS plate (b) after different cycles
Comparing the maximum wear depth and wear volume, it is found that the results of 690 TT alloy tube are lower than those of 405 SS plate. Additionally, the material loss in the center area of the 690 TT alloy tube is relatively small, indicating the superior wear resistance, compared with the 405 SS plate. This can be attributed to the face-centered cubic crystal structure of the 690 TT alloy tube, which offers more sliding directions, compared with the body-centered cubic crystal structure of the 405 SS plat
According to the adhesive wear theory, during the fretting process, softer materials tend to fracture and transfer onto the surface of harder materials, resulting in a W-shape wear depth profile on the 690 TT alloy tube. Furthermore, combined with EDS analysis, the Fe element content in the center area of the wear scar is significantly higher than that of the original 690 TT alloy tube. Therefore, it can be concluded that the pro-trusion in the center area originates from material transfer from the 405 SS plate. In contrast, the contour map of the wear depth on the 405 SS plate exhibits the typical U-shape.

Fig.8 SEM surface morphologies of 690 TT alloy tube after 1
Material transfer becomes noticeable on the 690 TT alloy tube surface after 1

Fig.9 SEM images (a–c), EDS mappings (d–o), and EDS line scanning results (p–r) of 690 TT alloy tube surface after 1
The center of the wear mark represents the total slip area, where the friction pair suffers the highest contact stress. This stress exceeds the elastic limit of the metal, resulting in relative sliding. Under the conditions of normal contact force and relative slip, material transfer and oxidation occur obviously, leading to the high content of Fe and O elements in the central region.
On the outer side of the wear mark, the normal contact force is not as high as that in the central area, even contact exists, and it remains within the elastic limit of the metal. Therefore, only cyclic compression occurs without exceeding the elastic limit. However, the adhesion may still occur, and the material transferred from 405 SS plate moves outward under repeated stress compression, resulting in the stacking and oxidation of the transferred material. This stacking effect can also be observed in Fig.
As a result, in certain slip regions, the content of Ni and Cr increases, and the surface elements are similar to the elements of 690 TT alloy tube. However, in the edge region with material stacking, the content of Fe and O elements increases again.
Fig.

Fig.10 Raman analysis of 690 TT alloy tube surface after different cycles
By comparing the absorption peaks with those of standard oxide
However, due to the close proximity of the absorption peaks of specific spinel components, it is difficult to determine the exact type of spinel oxide.

Fig.11 SEM cross-section images of 690 TT alloy tube after 1

Fig.12 Bright field TEM images (a, c, e) and EDS mappings (b, d, f) of center area of wear marks of 690 TT alloy tube after 1
According to Fig.
Compared with
No significant difference can be observed in the microstructure between the samples after 2×1
2Cr(OH)3→Cr2O3+3H2O | (1) |
Ni(OH)2→NiO+H2O | (2) |

Fig.13 HRTEM images of TBL in 690 TT alloy tube after 2×1
Fig.
NiO+2Fe | (3) |
Cr2O3+F | (4) |
Cr2O3+N | (5) |
After low cycles, the damage degree of the metal surface is relatively slight, and physical factors, such as hardness and stress field, are dominate influence factors. With the experiment further proceeding, the debris is corroded by water, and TBL and delaminated metal on the surface are crushed and adhere to the surface to form an oxide film. The influence of chemical factors, such as temperature and hydrochemical environment, is dominant in this case. The transformation of wear and corrosion mechanisms leads to the thinning of TBL during the transformation process, but ultimately the physical delamination and chemical corrosion processes reach the dynamic equilibrium. Therefore, the thickness of the oxide film firstly decreases, then increases, and finally tends to stabilize.
1) The depth contour of the wear marks of 690 TT alloy tube presents the W-shape, whereas that of the 405 SS plate presents the U-shape. The protrusion in the center of wear mark area of 690 TT alloy tube is caused by the material transfer from the 405 SS plate. The protrusion of the edge of the wear mark on surface is caused by the movement and stacking of the transfer material of 405 SS plate along the sliding directions during the reciprocating compression motion.
2) The dominant mechanism of fretting wear during 1
3) The main components in TBL are Fe3O4, spinel NiFe2O4, FeCr2O4, and (Ni, Fe)(Fe, Cr)2O4. A mixing layer exists beneath TBL in the sample after 1
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