Page 126 - 摩擦学学报2025年第10期

第 10 期 SU Yongyao, et al.: Exploring the Impact and Mechanism of CrN Interlayer on the Tribological ··· 1523

influence on the frictional properties. However, while nuclear reactors, preparing CrN on Zirconium alloy can
existing literatures predominantly delve into the effectively suppress Zr outward diffusion. It can be
oxidation and corrosion resistance properties of FeCrAl predicted that by introducing CrN layers between Zr and
coating, there remains a dearth of research concerning FeCrAl coating can effectively suppress Zr diffusion
their wear resistance properties, leaving the wear towards FeCrAl coating, simultaneously enhancing the
mechanism poorly understood. Hence, it is necessary to load-bearing capacity of the Zirconium alloy, thus
conduct in-depth investigations into the wear mechanism beneficial for obtaining excellent wear resistance as well
of FeCrAl coatings, which is crucial for the safe as oxidation resistance in nuclear fuel cladding coatings.
operation of FeCrAl coatings in pressurized water In this study, magnetron sputtering technology was
reactors. utilized to deposit an FeCrAl coating on the surface of
Transition metal nitrides, such as TiN, CrN, and the Zr-4 substrate, aiming to investigate the frictional
TiAlN offer a plethora of advantages, including mechanism of FeCrAl coating. To enhance the load-
exceptional hardness, superb wear resistance, and robust bearing capacity of Zr-4 substrate and further improved
high-temperature tolerance, rendering them indispen- the tribological property of FeCrAl coating, a CrN layer
sable for enhancing the surfaces of cutting tools, molds, was introduced between them. A comparative analysis of
[17] the mechanical properties and wear resistance of the two
and critical components . Among them, CrN exhibits
types of coatings was conducted in both air and B-Li
outstanding oxidation resistance and mechanical
water. The friction coefficient, wear rate, wear
properties, holding promise for application in coating the
surface of nuclear fuel cladding material. Daub et al [18] morphology, and debris were extensively examined to
gain insight into the wear mechanism of the coatings
investigated the short-term corrosion performance of
under air and B-Li water conditions. The results would
CrN in high-temperature steam and found that CrN
coating has good corrosion resistance. Lee et al [19] provided a theoretical foundation and technical guidance
for a deeper understanding of the tribological properties
revealed that CrN decomposes at 950 ℃, with the main
of FeCrAl-based coatings, which was of significant
[20]
oxidation product being Cr O . Liu et al revealed that
2
3
importance for the safe service of nuclear fuel cladding
CrN can inhibit the outward diffusion of Zr and prevent
materials.
the formation of low-melting Zr-Cr eutectic when it was
deposited on zirconium alloy, and decomposes to form
2 Materials and methods
Cr N in 1 000 ℃ steam while still providing a certain
2
protective effect. In summary, the oxidation resistance of 2.1 Coating preparation
CrN is lower at 1 000 ℃, and relying solely on CrN is FeCrAl coating was prepared on Zr-4 (10 mm×
not suffice to meet the demand for oxidation resistance 10 mm×1 mm) using a double-target co-sputtering
in cladding materials under conditions of coolant loss in technique. Fig. 1 showed the schematic diagram of the

Sputtering power supply (DC) Sputtering power supply (RF)

M
Mixer Fe CrAl Cr
Gas entrance Sample holder Vacuum chamber M Vacuum control system

Ar
N 2
DC pulse supply

Fig. 1 Schematic diagram of magnetron sputtering equipment