Influence of coating parameters on oxidation behavior of Cr-coated zirconium alloy for accident tolerant fuel claddings

The present paper is a narrative review focused on a few important aspects and moments of trends surrounding materials and methods in sustainable nuclear energy, as an expression of applied chemistry support for more efficiency and safety. In such context, the paper is focused firstly on increasing alloy performance by modifying compositions, and elaborating and testing novel coatings on Zr alloys and stainless steel. For future generation reactor systems, the paper proposes high entropy alloys presenting their composition selection and irradiation damage. Nowadays, when great uncertainties and complex social, environmental, and political factors influence energy type selection, any challenge in this field is based on the concept of increased security and materials performance leading to more investigations into applied science.

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“…or Si. Table 2 summarizes the main candidate materials as coatings for nuclear fuel cladding [ 35 , 37 , 47 , 55 , 56 , 57 , 58 , 59 , 60 , 61 ].…”

Section: Relations Between Microstructures and Alloys Performance Of ...mentioning

confidence: 99%

Aspects of Applied Chemistry Related to Future Goals of Safety and Efficiency in Materials Development for Nuclear Energy

Golgovici

Tudose²,

Diniasi³

et al. 2023

Molecules

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“…[30,31] Because the grains of the Cr coating are finer and denser, based on the electron backscattered diffraction in Figure 2, the higher density of Cr grain boundaries promotes the diffusion of Zr into the Cr coating. [32] Zr further diffused outward, resulting in an increase in the thickness of the ZrCr 2 layer. Massive intensive voids appeared between the base and the diffusion layer.…”

Section: Steam Oxidation Testsmentioning

confidence: 99%

Long‐term high‐temperature steam oxidation behavior of Cr‐coated Zircaloy‐4 alloy for accident tolerant fuel

Xiang

Yang

Chen

et al. 2022

Materials & Corrosion

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The Cr-coated Zircaloy-4 samples were prepared by arc ion plating to enhance the high-temperature oxidation resistance of Zircaloy-4 alloys for accident tolerant fuel claddings. The oxidation tests of the Cr coating were performed under 1473 K steam for 60, 120, and 240 min. The steam oxidation tests indicated that the Cr-coated Zircaloy-4 substrate had excellent hightemperature steam oxidation resistance to protect the fuel cladding from damage for at least 240 min. The weight gains and the thickness of the oxidation scale of the samples were measured to evaluate the oxidation kinetics of the Cr coating in 1473 K steam. In addition, the diffusion and interfacial evolution were analyzed during the oxidation process, and the steam oxidation behaviors of the Cr coatings were also discussed in detail.

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“…Kashkarov et al [ 46 ] prepared a 4.5 μm thick Cr coating with a dense and fine-grain structure by arc-magnetron sputtering and with better resistance to high-temperature steam oxidation than that of comparative samples (6–9 μm thick coatings with coarser columnar crystal) prepared by no-arc magnetron sputtering. 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 ].…”

Section: Introductionmentioning

confidence: 99%

“…Up to now, the control of Cr coatings has been performed by studying the effects of deposition parameters on their microstructures, such as surface droplet particles, crystal preferred orientation, grain structures, etc. [ 47 , 48 , 49 , 50 , 51 , 52 , 53 , 54 ]. However, these studies only compared single factor variables and could not distinguish between experimental error and the influence of various parameters.…”

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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Influence of coating parameters on oxidation behavior of Cr-coated zirconium alloy for accident tolerant fuel claddings

Cited by 44 publications

References 40 publications

Aspects of Applied Chemistry Related to Future Goals of Safety and Efficiency in Materials Development for Nuclear Energy

Aspects of Applied Chemistry Related to Future Goals of Safety and Efficiency in Materials Development for Nuclear Energy

Long‐term high‐temperature steam oxidation behavior of Cr‐coated Zircaloy‐4 alloy for accident tolerant fuel

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

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