There has been tremendous interest in the development of different innovative wear‐
resistant materials, which can help to reduce energy losses resulted from friction and wear …

The fretting wear behavior of Zr alloy cladding tube under mixed fretting regime in a high-
temperature pressurized water was investigated. The main wear mechanism is adhesive …

As a safe, clean, efficient and low-carbon energy, nuclear power is gaining increasing
interest in global energy development. However, working in the extremely harsh …

Fretting corrosion of as received and shot peened zirconium alloys exposed to high
temperature high pressure water is tested. High resolution characterization techniques are …

Fretting maps of Zr alloy tube under grid-to-rod configuration in high temperature
pressurised water were established. Running condition fretting map shows three fretting …

Fretting corrosion behavior and damage mechanism of Zr-4 alloy mated with Inconel 718
alloy under different fretting regimes in high temperature high pressure water were studied …

Cladding fuel rods supported in grids are important core components in pressurized water
nuclear reactors. Small rod-to-grid misalignments can occur during the core manufacturing …

Fretting wear tests of Zircaloy-4 alloy against Inconel 718 alloy were conducted on a fretting
wear rig. The contact state and fretting running characteristics of Zircaloy-4 alloy were …

The fretting wear behaviors and wear mechanism of the Cr-coated Zr–1Nb alloy cladding
tube mated with Zr-4 alloy dimple were investigated under different tangential …

Core components of nuclear reactor are generally made of zirconium alloys and some of
them are prone to low amplitude vibration leading to material wear at contact interface …