Fretting fatigue tests and crack initiation analysis on zircaloy tube specimens

被引：16

作者：

Tang, Lichen ^{[1
,2
]}

Ding, Shurong ^{[1
]}

Qian, Hao ^{[2
]}

Xie, Yongcheng ^{[2
]}

Huo, Yongzhong ^{[1
]}

机构：

[1] Fudan Univ, Dept Mech & Engn Sci, Shanghai 200433, Peoples R China

[2] Shanghai Nucl Engn Res & Design Inst, Shanghai 200233, Peoples R China

来源：

INTERNATIONAL JOURNAL OF FATIGUE | 2014年 / 63卷

基金：

高等学校博士学科点专项科研基金; 中国国家自然科学基金;

关键词：

Fretting fatigue test; Thin-wall tube specimen; Nuclear fuel cladding tube; Fretting fatigue initiation; CONTACT; SIMULATION; TI-6AL-4V; BEHAVIOR; WEAR;

D O I：

10.1016/j.ijfatigue.2014.01.020

中图分类号：

TH [机械、仪表工业];

学科分类号：

0802 ;

摘要：

Grid-to-rod fretting damage remains as a significant cause of nuclear fuel failure in pressurized water reactors (PWRs). By using a self-designed apparatus, fretting fatigue tests directly on thin-wall tube specimens were carried out. The S-N curve of the Zr-4 tube under some given fretting contact pressure is obtained, which is substantially lower than its life without fretting. And the initial crack occurs at the edge of the contact area where the amplitude of stress is confirmed to reach the maximum by FEM simulation. The position can be predicted by half-length of the initial contact region and the slip displacement. (C) 2014 Elsevier Ltd. All rights reserved.

引用

页码：154 / 161

页数：8

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