The fretting corrosion behaviors and the associated mechanisms of Zr alloy claddings with
and without Cr coating in the primary water (310° C/15.5 MPa) of the simulated pressurized …

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 …

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 …

Abstract Grid-to-rod (GTR) fretting wear was identified as the primary cause of fuel assembly
failure. A high temperature pressurized water fretting wear system was designed and …

An Inconel 690 alloy tube acting as a steam generator tube has been widely applied in the
second and third generations of nuclear power plants using pressurized water reactors …

Improving the high-temperature wear resistance of aero-engine components is critical. Laser
shock peening without coating (LSPwC) seems to have more potential because of lower …

The application of zirconium alloy in nuclear reactors is supported by its excellent
performance and corrosion resistance, but under the action of high-energy neutrons, the …

The fretting corrosion behaviors of Cr-coated Zr‐1Nb alloy claddings with Zr-4 dimple and
Inconel 718 spring in simulated PWR primary water were investigated. The results indicated …

TC21 titanium alloy possesses the advantage including high strength, low density, and great
resistance to damage. Combining it with surface modification technology, it is expected to …

Grid-to-rod fretting wear is an important factor causing the fuel failure in nuclear power
plants. Accident tolerant fuel (ATF) Cr coating and oxide ceramic coating have been …