Sliding wear and friction behavior of zirconium alloy with heat-treated Inconel718

被引：12
|
作者：
Kim, J. H.
Park, J. M.
Park, J. K. [1 ]
Jeon, K. L. [1 ]
机构：
[1] Korea Nucl Fuel, Nucl Fuel Technol Dept, Taejon 305353, South Korea
来源：
NUCLEAR ENGINEERING AND DESIGN | 2014年 / 269卷
关键词：
FRETTING WEAR;
D O I：
10.1016/j.nucengdes.2013.08.008
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
In water-cooled nuclear reactors, the sliding of fuel rod can lead to severe wear and it is an important issue to sustain the structural integrity of nuclear reactor. In the present study, sliding wear behavior of zirconium alloy in dry and water environment using Pin-On-Disk sliding wear tester was investigated. Wear resistance of zirconium alloy against heat-treated Inconel718 pin was examined at room temperature. Sliding wear tests were carried out at different sliding distance, axial load and sliding speed based on ASTM G99-05. The results of these experiments were verified with specific wear rate and coefficient of friction. The micro-mechanisms responsible for wear in zirconium alloy were identified to be microcutting and microcracking in dry environment. Moreover, micropitting and delamination were observed in water environment. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码：66 / 71
页数：6
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