| WANG Li-wen,CHEN Xu-dong,WANG Jun,FENG Shuo,TANG Rui,MO Kun,GUAN Xue-mei,ZHANG Qiang-sheng,CAI Zhen-bing.Fretting Wear Properties of Nuclear 2.25Cr-1Mo Steel in Different Environments[J],52(3):161-171 |
| Fretting Wear Properties of Nuclear 2.25Cr-1Mo Steel in Different Environments |
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| DOI：10.16490/j.cnki.issn.1001-3660.2023.03.013 |
| KeyWord:2.25Cr-1Mo steel heat transfer tube liquid sodium different environments fretting wear wear mechanism |
| Author | Institution |
| WANG Li-wen |
DEC Academy of Science and Technology Co., LTD, Chengdu , China |
| CHEN Xu-dong |
Tribology Research Institute, Southwest Jiaotong University, Chengdu , China |
| WANG Jun |
Tribology Research Institute, Southwest Jiaotong University, Chengdu , China |
| FENG Shuo |
Tribology Research Institute, Southwest Jiaotong University, Chengdu , China |
| TANG Rui |
Tribology Research Institute, Southwest Jiaotong University, Chengdu , China |
| MO Kun |
DEC Academy of Science and Technology Co., LTD, Chengdu , China |
| GUAN Xue-mei |
DEC Academy of Science and Technology Co., LTD, Chengdu , China |
| ZHANG Qiang-sheng |
Nuclear and Radiation Safety Center, MEE, Beijing , China |
| CAI Zhen-bing |
Tribology Research Institute, Southwest Jiaotong University, Chengdu , China |
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| Abstract: |
| In the steam generator of a sodium-cooled fast reactor, the fretting wear occurs between the heat transfer tubes and their anti-vibration bars due to the flow of the liquid sodium. In this study, the fretting wear behaviors of 2.25Cr-1Mo steel (candidate material for heat transfer tubes in sodium-cooled fast reactors) were investigated by using a self-made multi- atmosphere tangential fretting test rig. In order to simulate the actual working conditions of the heat transfer tube, a 450 ℃/liquid sodium environment was set. Three comparative environments, room temperature (RT)/air, RT/water, and 450 ℃/air, were used to comprehensively evaluate the wear behaviors of 2.25Cr-1Mo steel in different environments. The test adopts the form of tube/rod orthogonal point contact, and the test parameters are as follows:the normal load is 20 N; the frequency is 5 Hz; the displacement amplitude is 50 μm; the number of cycles is 105 and 2×105. Before the test, the hardness of 2.25Cr-1Mo steel at RT and 450 ℃ was tested by a Vickers hardness tester. After the test, the three-dimensional morphology of the wear scar was measured by Bruker white light interference microscope, and the cross-sectional profile and wear volume were obtained. Scanning electron microscope (SEM) and energy dispersive spectrometer (EDS) were used to analyze the micromorphology and tribo-chemical reaction of the wear scar surface and cross-sectional. Results show that the hardness of 2.25Cr-1Mo steel will decrease significantly at 450 ℃, and exhibits different wear properties in different environments. The 2.25Cr-1Mo steel has the worst wear resistance in liquid sodium at 450 ℃, while the best wear resistance in water at RT. The sodium reduces the lubricating oxide layer to metal, accelerating the wear, while the water lubricates and reduces wear. Therefore, the wear rate of 2.25Cr-1Mo steel is the largest in liquid sodium at 450 ℃ (4.17×10‒6 mm3/(N.m)) and the smallest in water at RT (0.32×10‒6 mm3/(N.m)). The wear resistance of 2.25Cr-1Mo steel in the air is affected by the temperature. In the first 105 cycles (early severe wear stage), the wear rate at RT is smaller, and in the last 105 cycles (late stable wear stage), the wear rate at 450 ℃ is even smaller. In the early stage of wear, the 2.25Cr-1Mo steel at high temperature is more easily deformed and peeled off under the combined action of thermal effect and mechanical force, so a larger wear volume is measured, while in the later stage of wear, the material under high temperature is more likely to produce a thicker "glaze layer" at the wear interface, which has lubricating and anti-friction properties. Finally, the main wear mechanism of 2.25Cr-1Mo steel in the air at RT is delamination, spalling and oxidative wear; as the temperature rises to 450 ℃, the oxidative wear in the air intensifies, accompanied by delamination and "forging flow lines"; and in water at RT is abrasive wear and oxidative wear; and in liquid sodium at 450 ℃ is abrasive wear, adhesive wear and "forging flow lines |
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