Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4

Umretiya, Rajnikant V.; Elward, Barret; Lee, Donghwi; Anderson, Mark; Rebak, Raúl B.; Rojas, Jessika V.

doi:10.1016/j.jnucmat.2020.152420

Cited by 60 publications

(15 citation statements)

References 129 publications

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“…The interplanar distances are calculated to be 2.0382, 1.4417 and 1.1773 nm, respectively, which are consistent with the PDF card values. The diffraction peak of the (110) plane is much stronger than the other two planes, consistent with results obtained during other studies [ 27 , 48 , 49 , 59 , 60 ]. This is the close-packed plane of a BCC crystal, which will have the lowest surface energy and smallest growth energy barrier.…”

Section: Resultssupporting

confidence: 92%

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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Section: Resultssupporting

confidence: 92%

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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“…3 The nuclear community is considering two main strategies to develop new fuel technology 4 : (1) application of coatings to Zircaloy cladding and (2) development of non-Zircaloy monolithic alternative materials. A number of studies have demonstrated that ceramic coatings such as SiC, 5 TiAlCrN, 6 and CrN, 7 and metallic coatings such as FeCrAl 8 and Cr [9][10][11][12] have excellent resistance to oxidation at higher temperature. Similarly, FeCrAl alloys have shown outstanding high-temperature (£ 1000°C) oxidation resistance, [13][14][15] remarkable stability of microstructural and mechanical properties at different radiation doses, 16 and high ultimate tensile and yield strength at different temperatures.…”

Section: Introductionmentioning

confidence: 99%

Oxidation Resistance in 1200°C Steam of a FeCrAl Alloy Fabricated by Three Metallurgical Processes

Hoffman

Umretiya

Gupta

et al. 2022

JOM

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FeCrAl alloys are a leading candidate material for accident tolerant fuel cladding due to their good performance in both normal light-water reactor operating conditions as well as their resilience to high-temperature accident scenarios. For commercial-scale production, new fabrication techniques need to be investigated. In this study, the effects of fabrication methods on the high-temperature steam oxidation performance of C26M (Fe12Cr6Al2Mo in wt.%) were investigated. Three variants of C26M were manufactured: wrought (cast and forged) (WC26M), powder metallurgy hot isostatic pressing (PMC26M), and laser powder bed fusion additive manufacturing (AMC26M). All three variants were exposed to steam at 1200°C for 2 h. Results showed no significant variation in mass change between the variants after steam exposure. All three variants effectively formed stable protective alumina films with ~0.6–1.3 µm thickness. This study suggests FeCrAl alloys have excellent resilience to high-temperature steam in nuclear reactor accident scenarios regardless of the fabrication method.

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“…As long as the Cr coating is intact/protective, the microstructure of the Cr coatings is the key characteristic in normal operation and accident conditions [165,[168][169][170]. It has been shown that the activation energy of oxidation is higher for dense Cr coatings compared to columnar ones.…”

Section: Microstructure and Thickness Of The Coatingsmentioning

confidence: 99%

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

et al. 2021

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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.

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Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4

Cited by 60 publications

References 129 publications

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

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

Oxidation Resistance in 1200°C Steam of a FeCrAl Alloy Fabricated by Three Metallurgical Processes

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

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