Abstract:In order to improve the high‐temperature steam oxidation resistance of Zircaloy fuel claddings, chromium‐containing coatings (Cr3C2‐NiCr and NiCr) were deposited on a Zr‐4 substrate by air plasma spray. The steam oxidation resistance of the two coatings was evaluated at 1200 °C under atmospheric pressure. The weight changes, phase compositions, and microstructures of the coatings before and after the oxidation test of 1 h were characterized. Results revealed that the Cr3C2‐NiCr coating effectively protected Zr… Show more
“…However, the coated samples showed poor corrosion resistance in supercritical water at 400 • C and 10.3 MPa, caused by a bimetallic effect (this coating can build up bimetallic couple with the Zr-2.5Nb alloy, resulting in the acceleration of the corrosion rate). Yang et al demonstrated high oxidation resistance of 120 µm-thick HVOF Cr 3 C 2 -NiCr coating at 1200 • C in steam for 1 h due to the formation of a dense chromia scale [149]. However, the high coating thickness and heterogeneous/porous microstructure formed by the HVOF method may limit the usefulness of such coatings for ATF Zr claddings.…”
Zirconium-based alloys have served the nuclear industry for several decades due to their acceptable properties for nuclear cores of light water reactors (LWRs). However, severe accidents in LWRs have directed research and development of accident tolerant fuel (ATF) concepts that aim to improve nuclear fuel safety during normal operation, operational transients and possible accident scenarios. This review introduces the latest results in the development of protective coatings for ATF claddings based on Zr alloys, involving their behavior under normal and accident conditions in LWRs. Great attention has been paid to the protection and oxidation mechanisms of coated claddings, as well as to the mutual interdiffusion between coatings and zirconium alloys. An overview of recent developments in barrier coatings is introduced, and possible barrier layers and structure designs for suppressing mutual diffusion are proposed.
“…However, the coated samples showed poor corrosion resistance in supercritical water at 400 • C and 10.3 MPa, caused by a bimetallic effect (this coating can build up bimetallic couple with the Zr-2.5Nb alloy, resulting in the acceleration of the corrosion rate). Yang et al demonstrated high oxidation resistance of 120 µm-thick HVOF Cr 3 C 2 -NiCr coating at 1200 • C in steam for 1 h due to the formation of a dense chromia scale [149]. However, the high coating thickness and heterogeneous/porous microstructure formed by the HVOF method may limit the usefulness of such coatings for ATF Zr claddings.…”
Zirconium-based alloys have served the nuclear industry for several decades due to their acceptable properties for nuclear cores of light water reactors (LWRs). However, severe accidents in LWRs have directed research and development of accident tolerant fuel (ATF) concepts that aim to improve nuclear fuel safety during normal operation, operational transients and possible accident scenarios. This review introduces the latest results in the development of protective coatings for ATF claddings based on Zr alloys, involving their behavior under normal and accident conditions in LWRs. Great attention has been paid to the protection and oxidation mechanisms of coated claddings, as well as to the mutual interdiffusion between coatings and zirconium alloys. An overview of recent developments in barrier coatings is introduced, and possible barrier layers and structure designs for suppressing mutual diffusion are proposed.
“…Up to now, many types of coating materials have been developed, including MAX phase coatings [10][11][12][13][14], carbide coatings [15,16], nitride coatings [17][18][19][20], pure metal coatings [21][22][23][24][25][26] and alloy coatings [27][28][29][30][31][32]. Previous studies show that MAX phase coatings such as Ti-Al-C and Cr-Al-C are susceptible to cracking through the coating during heat treatment, water corrosion, and high temperature steam oxidation [33,34].…”
“…However, the HT oxidation experiments performed so far have focused mainly on the performance of the ideal coating without defects [11][12][13][14]. According to existing studies, the HT steam oxidation process of Cr-coated Zr-based alloys can be divided into three groups.…”
The present study focuses on the evaluation of the mechanical properties degradation of Cr-coated Zr-alloy fuel cladding. The main objective of the work is to find a suitable methodology to evaluate the mechanical properties degradation of coated cladding by performing several separate effects experiments.Apart from the many positive effects of protective coatings on the overall cladding properties, coatings’ general disadvantage is their reduced ability to tolerate plastic strain. Therefore, coating cracks might occur in the first stage of the hypothetical Loss of Coolant Accident (LOCA). The study is unique because of the consideration of coating cracks. Prior to the high-temperature (HT) oxidation, samples were subjected to either a scratch test or burst test, resulting in the creation of coating defects. The subsequent evaluation of the obtained data consisted of wavelength dispersion spectroscopy (WDS) and optical microscopy analysis and hydrogen content measurements.
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