Recent Advances in Protective Coatings for Accident Tolerant Zr-Based Fuel Claddings

Kashkarov, Egor; Afornu, Bright Kwame; Sidelev, Dmitrii V.; Krinitcyn, M. G.; Gouws, Veronica; Лидер, А. М.

doi:10.3390/coatings11050557

Cited by 73 publications

(32 citation statements)

References 162 publications

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“…Thus, a barrier sublayer (e.g., Mo, Ta, etc.) should be additionally applied for prevention of Cr-Zr interdiffusion at temperatures higher 1300 • C [39,40].…”

Section: Discussionmentioning

confidence: 99%

High-Temperature Oxidation of Cr-Coated Resistance Upset Welds Made from E110 Alloy

2021

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The resistance upset welds (RUW) made from E110 alloy without and with Cr coatings were oxidized in air atmosphere at 1100 °C for 2, 10 and 30 min. The cross-section microstructure, elemental composition and hardness were studied before and after oxidation using optical and scanning electron microscopy, and indentations in welding region. The RUW welding does not noticeably change oxidation kinetics of E110 alloy. The most crucial effect has surface non-regularities formed after welding, which prevent uniform coating deposition on full surface of welded cladding tube and end plug. Cr coating deposition can strongly reduce oxidation of welded E110 alloy, while additional post-processing treatment should be applied to improve surface morphology after RUW welding. Several suggestions favorable to development of ATF Zr-based claddings using Cr coating deposition on welded nuclear rods were discussed.

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“…Thus, a barrier sublayer (e.g., Mo, Ta, etc.) should be additionally applied for prevention of Cr-Zr interdiffusion at temperatures higher 1300 • C [39,40].…”

Section: Discussionmentioning

confidence: 99%

High-Temperature Oxidation of Cr-Coated Resistance Upset Welds Made from E110 Alloy

2021

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“…During these early studies, metallic chromium coatings have shown an encouraging behavior with excellent corrosion resistance in nominal conditions, and a significant enhancement of the HT steam oxidation behavior in accidental conditions, when compared with the reference uncoated zirconium based cladding materials [11]. More recently, the studies have confirmed the good behavior of Cr coatings in steam environment at HT, up to at least 1300 • C [19][20][21][22].…”

Section: Introductionmentioning

confidence: 90%

“…CrN coatings demonstrate barrier properties at temperatures above 1350 • C, but only for thick interlayers. It is known that decomposition of CrN with formation of zirconium nitride, despite the barrier properties of ceramic coatings which are advantageous, are brittle, and small changes in temperature can lead to the formation of micro cracks and coating failures [20]. Musil proposed multilayers to prevent cracking CrN/Cr (250/250 nm) coatings against Cr-Zr inter-diffusion during heating up to 1400 • C [26,27].…”

Section: Introductionmentioning

confidence: 99%

Corrosion Behavior of Chromium Coated Zy-4 Cladding under CANDU Primary Circuit Conditions

et al. 2021

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The manuscript is focused on corrosion behavior of a Cr coating under CANada Deuterium Uranium(CANDU) primary circuit conditions. The Cr coating is obtained via the thermionic vacuum arc procedure on Zircaloy -4 cladding. The surface coating characterization was performed using metallographic analysis and scanning electron microscopy (SEM) with an energy dispersive spectra detector (EDS), X-ray diffraction (XRD), and X-ray photoelectron spectroscopy (XPS) investigations. The thickness of the Cr coating determined from SEM images is around 500 nm layers After the autoclaving period, the thickness of the samples increased in time slowly. The kinetic of oxidation established a logarithmic oxidation law. The corrosion tests for various autoclaving periods of time include electrochemical impedance spectroscopy (EIS) and potentiodynamic tests, permitting computing porosity and efficiency of protection. All surface investigations sustain electrochemical results and promote the Cr coating on Zircaloy-4 alloy autoclaved for 3024 h as the best corrosion resistance based on decrease in corrosion current density values simultaneously with the increase of the time spent in autoclave. A slow increase of Vickers micro hardness was observed as a function of the autoclaved period as well. The value reached for 3024 h being 219 Kgf/mm2 compared with 210 Kgf/mm2 value before autoclaving.

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“…To avoid such a scenario, the oxidation resistance of the nuclear fuel claddings can be improved through the concepts of Enhanced Accident Tolerant Fuel (EATF) [ 1 ]. Among the different evolutive (i.e., short-term) EATF concepts studied so far, Cr-coated Zr-based claddings appear to be one of the most promising [ 2 , 3 , 4 , 5 ]. In doing so, metallic chromium-based coatings are deposited on zirconium cladding tubes using different processes.…”

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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Recent Advances in Protective Coatings for Accident Tolerant Zr-Based Fuel Claddings

Cited by 73 publications

References 162 publications

High-Temperature Oxidation of Cr-Coated Resistance Upset Welds Made from E110 Alloy

High-Temperature Oxidation of Cr-Coated Resistance Upset Welds Made from E110 Alloy

Corrosion Behavior of Chromium Coated Zy-4 Cladding under CANDU Primary Circuit Conditions

Radiation-Induced Sharpening in Cr-Coated Zirconium Alloy

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