Sliding wear and friction behaviour of zircaloy-4 in water

被引：27

作者：

Sharma, Garima ^{[1
]}

Limaye, P. K. ^{[2
]}

Jadhav, D. T. ^{[2
]}

机构：

[1] Bhabha Atom Res Ctr, Struct Met Sect, Bombay 400085, Maharashtra, India

[2] Bhabha Atom Res Ctr, Refuelling Technol Div, Bombay 400085, Maharashtra, India

来源：

JOURNAL OF NUCLEAR MATERIALS | 2009年 / 394卷 / 2-3期

关键词：

PRESSURE TUBES; FRETTING WEAR; ZIRCONIUM; PRECIPITATION;

D O I：

10.1016/j.jnucmat.2009.09.001

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

In water cooled nuclear reactors, the sliding of fuel bundles in fuel channel handling system can lead to severe wear and it is an important topic to study. In the present study, sliding wear behaviour of zircaloy-4 was investigated in water (pH similar to 10.5) using ball-on-plate sliding wear tester. Sliding wear resistance zircaloy-4 against SS 316 was examined at room temperature. Sliding wear tests were carried out at different load and sliding frequencies. The coefficient of friction of zircaloy-4 was also measured during each tests and it was found to decrease slightly with the increase in applied load. The micro-mechanisms responsible for wear in zircaloy-4 were identified to be microcutting, micropitting and microcracking of deformed subsurface zones in water. (C) 2009 Elsevier B.V. All rights reserved.

引用

页码：151 / 154

页数：4

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