CAJ | 학술논문

在试验温度为20~25℃(air)、300℃(air)、300℃(N 2)，法向载荷为(F n )50和100 N，位移幅值为60~200μm的条件下，采用PLINT高温微动磨损试验机研究核电蒸汽发生器传热管材Inconel690与1Cr13不锈钢圆柱配对副在滑移区的微动磨损特性。结果表明：当法向载荷一定时，随位移幅值增加，在高温大气中，微动摩擦因数逐渐升高；而高温氮气中，摩擦因数降低。当载荷和位移相同时，Inconel690在高温大气中磨损较轻，在高温氮气中损伤较严重。在高温大气和高温氮气中磨痕表面均出现不同程度摩擦氧化，主要生成Fe、Ni、Cr等合金元素的氧化物。Inconel690的磨损机制主要表现为磨粒磨损、摩擦氧化和剥层磨损的共同作用。
재시험온도위20~25℃(air)、300℃(air)、300℃(N 2)，법향재하위(F n )50화100 N，위이폭치위60~200μm적조건하，채용PLINT고온미동마손시험궤연구핵전증기발생기전열관재Inconel690여1Cr13불수강원주배대부재활이구적미동마손특성。결과표명：당법향재하일정시，수위이폭치증가，재고온대기중，미동마찰인수축점승고；이고온담기중，마찰인수강저。당재하화위이상동시，Inconel690재고온대기중마손교경，재고온담기중손상교엄중。재고온대기화고온담기중마흔표면균출현불동정도마찰양화，주요생성Fe、Ni、Cr등합금원소적양화물。Inconel690적마손궤제주요표현위마립마손、마찰양화화박층마손적공동작용。
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 ℃(N 2 ), 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.