Published November 2009 | Version v1
Journal article

Sliding wear and friction behaviour of zircaloy-4 in water

  • 1. Structural Metallurgy Section, BARC, Mumbai 400 085 (India)
  • 2. Refuelling Technology Division, BARC, Mumbai 400 085 (India)

Description

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 ∼ 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.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2009.09.001

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2009.09.001;
PII
S0022-3115(09)00772-7;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
394
Journal Issue
2-3
Journal Page Range
p. 151-154
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

Copyright
Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.