A study on fretting fatigue characteristics of Inconel 690 at high temperature

被引：37

作者：

Kwon, Jae-do ^{[2
]}

Jeung, Han-kyu ^{[1
]}

Chung, Il-sup ^{[2
]}

Yoon, Dong-hwan ^{[3
]}

Park, Dae-kyu ^{[4
]}

机构：

[1] Yeungnam Univ, Grad Sch Mech Engn, Kyongsan 712749, South Korea

[2] Yeungnam Univ, Dept Mech Engn, Kyongsan 712749, South Korea

[3] Korea Aerosp Res Inst, Taejon, South Korea

[4] Korea Text Machinary Inst, Kyongsan, South Korea

来源：

TRIBOLOGY INTERNATIONAL | 2011年 / 44卷 / 11期

关键词：

Steam generator tube; Inconel; 690; Fretting fatigue strength; Friction force;

D O I：

10.1016/j.triboint.2010.11.006

中图分类号：

TH [机械、仪表工业];

学科分类号：

0802 ;

摘要：

Inconel 690 alloy is used in nuclear power plant steam generator tubes. Fretting fatigue experiments were performed on Inconel 690 specimens at room temperature and at the nuclear power plant operating temperature of 320 degrees C. By comparing the fretting fatigue test data at room temperature and 320 degrees C, this study analyzed the change in characteristics related to the fatigue limit at 10(7) cycles. In addition, this study attempted to measure changes in the friction force for repetitive cycles in fretting fatigue tests, and analyzed the mechanism of fretting fatigue by observing the fracture surfaces and performing spectrum analysis. (C) 2010 Elsevier Ltd. All rights reserved.

引用

页码：1483 / 1487

页数：5

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