(1. 西南交通大學(xué) 摩擦學(xué)研究所，成都 610031；
2. 中國核動力研究設(shè)計院設(shè)計所，成都 610041)
摘 要: 在試驗溫度為20~25 ℃(air)、300 ℃(air)、300 ℃(N2)，法向載荷為(Fn)50和100 N，位移幅值為60~200 μm的條件下，采用PLINT高溫微動磨損試驗機研究核電蒸汽發(fā)生器傳熱管材Inconel690與1Cr13不銹鋼圓柱配對副在滑移區(qū)的微動磨損特性。結(jié)果表明：當法向載荷一定時，隨位移幅值增加，在高溫大氣中，微動摩擦因數(shù)逐漸升高；而高溫氮氣中，摩擦因數(shù)降低。當載荷和位移相同時，Inconel690在高溫大氣中磨損較輕，在高溫氮氣中損傷較嚴重。在高溫大氣和高溫氮氣中磨痕表面均出現(xiàn)不同程度摩擦氧化，主要生成Fe、Ni、Cr等合金元素的氧化物。Inconel690的磨損機制主要表現(xiàn)為磨粒磨損、摩擦氧化和剝層磨損的共同作用。
關(guān)鍵字: Inconel690；高溫氮氣；微動磨損；摩擦氧化；剝層磨損
（1. Tribology Research Institute, Southwest Jiaotong University, Chengdu 610031, China;
2. Institute, Nuclear Power Institute of China, Chengdu 610041, China）
Abstract:The fretting wear behavior of the steam generator tubes material Inconel690 of nuclear power was investigated against 1Cr13 stainless steel by PLINT high temperature fretting tester in the slip regime under the conditions of the temperatures of 20-25 ℃(air), 300 ℃(air) and 300 ℃(N2), the normal loads of 50 and 100 N, and the displacement amplitudes from 60 μm to 200 μm. The results show that the fretting friction coefficient gradually increases as the increase of displacement amplitude under the same normal load in the high-temperature air, however, the friction coefficient decreases in the high-temperature nitrogen. The damage degree of Inconel690 is slight in the high-temperature air, but more serious in the high-temperature nitrogen at the same load and displacement. In the high-temperature air and nitrogen atmosphere, the wear surface occurs different degrees of friction oxidation which generates mainly oxidation of Fe, Ni, Cr and so on. The abrasive wear, friction oxidation and delamination are main wear mechanisms of Inconel690.
Key words: Inconel690; high-temperature nitrogen; fretting wear; friction oxidation; delamination
