Formation of voids in the Cr coatings with (110)-preferred orientation prepared by arc ion plating under an Au+ irradiation of 20 dpa

Gong, Wenjuan; Chen, Huan; Zhan, Changyong; Du, Peinan; Zhang, Ruiqian; Wang, Yu; Wei, Tianguo; Yang, Hongyan; Zou, Yu; Yang, Jijun

doi:10.1016/j.surfcoat.2021.127750

Cited by 12 publications

(3 citation statements)

References 29 publications

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“…They also observed the formation of cavities and reported that the swelling caused by void formation is maximum at 500 °C. Gong et al [ 11 ] also observed voids and brought new precisions on their formation by showing that the void size and density depend on the Cr grain texture: void size decreases while void density increases with increasing the (110)-oriented crystallinity. Although various authors reported voids, they are not the only defects observed under irradiation.…”

Section: Introductionmentioning

confidence: 99%

Radiation-Induced Sharpening in Cr-Coated Zirconium Alloy

Ribis

Guillou

et al. 2022

Materials

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To improve the safety of nuclear power plants, a Cr protective layer is deposited on zirconium alloys to enhance oxidation resistance of the nuclear fuel cladding during both in-service and hypothetical accidental transients at High Temperature (HT) in Light Water Reactors. The formation of the Cr2O3 film on the coating surface considerably helps in reducing the oxidation kinetics of the zirconium alloy, especially during hypothetic Loss of Coolant Accident (LOCA). However, if the Cr coating is successful to increase the oxidation resistance at HT of the zirconium substrate, for in-service conditions, under neutron irradiation, Cr desquamation has to be avoided to guarantee a safe use of the Cr-coated zirconium alloys. Therefore, the adhesion properties have to be maintained despite the structural defects created by sustained neutron irradiation in the reactor environment. This paper proposes to study the behavior of the Zircaloy-Cr interface of a first generation Cr-coated material during a specific in situ ion irradiation. As deposited, the Cr-coated sample presents a f.c.c. C15 Laves-type intermetallic phase at the interface with off-stoichiometric composition. After irradiation and for the specific conditions applied, this interfacial phase has significantly dissolved. Energy Dispersion Spectroscopy revealed that the dissolution was accompanied by a counterintuitive “sharpening” effect.

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Section: Introductionmentioning

confidence: 99%

Radiation-Induced Sharpening in Cr-Coated Zirconium Alloy

Ribis

Guillou

et al. 2022

Materials

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“…Consequently, many coatings such as Cr and Cr-based alloys [ 14 , 15 , 16 ], nitride ceramics [ 17 , 18 , 19 ], FeCrAl alloys [ 20 , 21 , 22 ] and MAX phase ceramics [ 23 , 24 , 25 ] are used worldwide. Among them, Cr coatings show resistance to pressurized-water corrosion [ 26 , 27 ], friction and wear [ 16 , 28 ], high-temperature steam oxidation [ 29 , 30 , 31 , 32 ] and ion or neutron irradiation [ 33 , 34 , 35 , 36 ], and hence become the most promising candidate for advanced ATF cladding coatings. At present, the most important task for the development of pure Cr coatings on Zr alloy claddings is to precisely control the coating to meet the requirements of engineering design.…”

Section: Introductionmentioning

confidence: 99%

“…Furthermore, the differences in the processing parameters of the same method show great differences in high-temperature oxidation resistance [ 47 , 48 , 49 , 50 ]. Our recent studies found that increases in the (110) preferred orientation of the AIP Cr coatings resulted in a decrease in the size and number of cavities during Au + ion irradiation (up to 20 dpa) [ 34 ]. Our ongoing research also indicates that different process parameters in the same technology would affect both the resistance to coating cracking in mechanical tests and the degradation behavior of the Cr coatings during high-temperature oxidation.…”

Section: Introductionmentioning

confidence: 99%

An Orthogonal Experimental Study on the Preparation of Cr Coatings on Long-Size Zr Alloy Tubes by Arc Ion Plating

Chen

Wang

et al. 2022

Materials

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Cr-coated Zr alloys are widely considered the most promising accident-tolerant fuel (ATF) cladding materials for engineering applications in the near term. In this work, Cr coatings were prepared on the surfaces of 1400 mm long N36 cladding tubes using an industrial multiple arc source system. Orthogonal analyses were conducted to demonstrate the significance level of various process parameters influencing the characteristics of coatings (surface roughness, defects, crystal orientation, grain structure, etc.). The results show that the arc current mainly affects the coating deposition rate and the droplet particles on the surface or inside the coatings; however, the crystal preferred orientation and grain structure are more significantly influenced by the gas pressure and negative bias voltage, respectively. Then, the underlying mechanisms are carefully discussed. At last, a set of systemic methods to control the quality and microstructures of Cr coatings are summarized.

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