Recent studies on potential accident-tolerant fuel-cladding systems in light water reactors

Chen, Shengli; He, Xiujie; Yuan, Cenxi

doi:10.1007/s41365-020-0741-9

Cited by 49 publications

(16 citation statements)

References 135 publications

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“…This is twice lower than the allowable swelling value (~5%) for reactor materials. Cr-Al alloy coatings show better oxidation resistance than pure chromium [80,103,104]. However, a more complex and heterogeneous structure of the oxide layers forms after oxidation [105], which requires more detailed studies under long-term HT steam oxidation, as well as B-DBA conditions.…”

Section: Chromium-based 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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Section: Chromium-based Coatingsmentioning

confidence: 99%

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

et al. 2021

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“…5. (1,2); FeCrAl (3,4), and CrAl (5) in a solution of 3% NaCl Analysis of the polarization curves (see Fig. 5) shows that the potential for the onset of corrosion dissolution (φnk) takes values for coatings #1-5, respectively: -0.179; -0.3; -0.25; -0.2; +0.05 V. It is seen that the values of φnk for coatings #1-4 are close and negative, and for #5 it differs significantly and is shifted to the positive region, which indicates a higher corrosion resistance of CrAl coating.…”

Section: Fig 3 Coatings Mass Loss Depending On the Time Of Cavitation Wear: Fecr (1 2); Fecral (3 4) And Cral (5)mentioning

confidence: 99%

“…Photos and mass gain of the Zr1Nb alloy cladding fragments after oxidation in air at a temperature of 1150 °C for 60 min: uncoated, with protective coatings FeCr (1, 2); FeCrAl (3,4) Studies by scanning electron microscopy and microprobe elemental analysis showed that in the coatings after oxidation forms thin ~ 3…5 μm dense oxide layers of complex elemental composition, and on the zirconium alloy a porous oxide layer ZrO 2 is formed with the thickness of ~ 150 μm, which does not provide protection of the tube. Table 5 presents the SEM images of the cross sections of the fragments of the fuel tubes before and after oxidation.…”

Section: Tablementioning

confidence: 99%

“…The use of protective coatings to increase the service life and increase safety in accident conditions, especially the claddings of fuel rods within the ATFC (accident-tolerant fuel cladding) concept, is an alternative and cost-effective solution, because it can be used existing zirconium claddings and their technologies manufacturing [2,3]. Various candidate materials were studied as protective coatings on zirconium alloy fuel rods, which have a lower oxidation rate in water vapor and air at temperatures of 1000…1200 °C [2]: SiC [3,4], Cr [5,6], Cr 2 AlC [7], CrN [8], Cr-Al [9][10][11], FeCrAl [12][13][14][15][16]. FeCrAl-based coatings can be more resistant, compared with chromium, to oxidation in water vapor at high temperatures due to the formation on the surface of a protective film of Al 2 O 3 [17].…”

Section: Introductionmentioning

confidence: 99%

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STRUCTURE AND PROPERTIES OF FeCr, CrAl AND FeCrAl COATINGS DEPOSITED BY CATHODIC ARC EVAPORATION

Василенко¹,

Voyevodin²,

Белоус³

et al. 2021

Problems of Atomic Science and Technology

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Protective coatings with different compositions of Fe, Cr, and Al were deposited by cathodic arc evaporation method on fragments of Zr1Nb alloy fuel claddings. The influence of the composition and structural state of the developed coatings on their physical and mechanical properties (microhardness, resistance to corrosion and cavitation and abrasive wear) has been studied. It is shown that the optimal combination of mechanical properties and high resistance to oxidation from a series of studied coatings FeCr, FeCrAl, and CrAl have coatings of the FeCrAl system with a concentration of Cr ~ 22 at.% and Al ~ 14.3 at.%. It was found that protective coatings such as FeCr, FeCrAl, and CrAl with a thickness of ~ 12 μm significantly increase the resistance to oxidation and prevent the destruction of fuel claddings under oxidation in air at a temperature of 1150 °C for 1 h.

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“…However, in an extreme environment under accident conditions, zircaloy claddings suffer from rapid oxidation and severely depleted mechanical properties, causing hydrogen generation and catastrophic failure. Hence, in recent years, it has attracted worldwide interest to develop enhanced accidenttolerant fuel (ATF) cladding materials to enhance the accident resistance of claddings during beyond-design-basis scenarios [1][2][3][4][5]. Among several reported potential methods, surface coating with superior oxidation resistance deposited on the zircaloy cladding has been considered one of the near-term solutions for next-generation ATF systems [2,6].…”

Section: Introductionmentioning

confidence: 99%

Interdiffusion behavior between Cr and Zr and its effect on the microcracking behavior in the Cr-coated Zr-4 alloy

Jiang¹,

Wang²,

Du³

et al. 2021

NUCL SCI TECH

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High-temperature chromium (Cr)-zirconium (Zr) interdiffusion commonly occurs in Cr-coated zircaloys applied for enhanced accident-tolerant fuel (ATF) claddings. Such interdiffusion changes the interfacial microstructure and thus the fracture mechanism of the coating under external loading. In this study, the interdiffusion behavior in a magnetron sputtered Cr coating deposited on a Zr-4 alloy was studied in a vacuum environment at 1160 °C. In addition, the effect of interdiffusion on the microcracking behavior of the Cr coating was determined by in situ three-point bending tests. The experimental results show that the interdiffusion behavior resulted in the formation of a ZrCr 2 layer, accompanied by the consumption of Cr coating and interfacial roughening. The growth of the diffusion layer followed a nearly parabolic law with respect to annealing time, and the residual stress of the annealed coating decreased with increasing annealing time. Under external loading, a large number of cracks were generated in the brittle interlayer, and some interfacial cracks were formed and grew at the ZrCr 2 /Zr-4 interface. Despite the remarkable microcracks in the ZrCr 2 layer, the vacuum-annealed Cr coating has significantly fewer cracks than the original coating, mainly because of the recrystallization of the coating during annealing.

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Recent studies on potential accident-tolerant fuel-cladding systems in light water reactors

Cited by 49 publications

References 135 publications

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

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

STRUCTURE AND PROPERTIES OF FeCr, CrAl AND FeCrAl COATINGS DEPOSITED BY CATHODIC ARC EVAPORATION

Interdiffusion behavior between Cr and Zr and its effect on the microcracking behavior in the Cr-coated Zr-4 alloy

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