Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding

Doyle, Peter J.; Koyanagi, Takaaki; Ang, Caen; Snead, Lance Lewis; Mouche, Peter A.; Katoh, Yutai; Raiman, Stephen S.

doi:10.1016/j.jnucmat.2020.152203

Cited by 40 publications

(20 citation statements)

References 53 publications

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“…Zirconium carbide can be potentially used since it has an intermediate CTE and thermal conductivity comparable to that of Zr. Silicon carbide, and with a cubic (3C) structure that is well-studied since it is one of the most prospective materials for ATF claddings [189][190][191]. However, its significantly lower CTE compared to Cr and Zr, as well as possible reactions with Zr, limit its application as a barrier interlayer coating for B-DBA conditions.…”

Section: Interdiffusion and Eutectics Under B-dba Conditionsmentioning

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: Interdiffusion and Eutectics Under B-dba Conditionsmentioning

confidence: 99%

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

et al. 2021

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“…The stress state of the coating is also affected by other phenomena, such as irradiation swelling and the diffusion kinetics. Irradiation swelling of the coating can introduce voids inside the coating which change the stress state of the coating [20]. In addition, the diffusion kinetics and the thickness of the coating should be investigated to analyze the interdiffusion of Cr and Zr and the formation and growth of the Laves phase and to quantify their impact on the longevity of the coated cladding.…”

Section: Thermal Expansion and Residual Stressmentioning

confidence: 99%

“…The slope of a plot of dψ vs. sin 2 ψ, where dψ is assumed to be equal to dψ=0, delivers the stress along the Sϕ direction, if E and ν are known [23,25]. This method, known as the sin 2 ψ technique, is easy to apply to a coating of only a few microns and can also be applied to irradiated material, which makes this nondestructive technique a valuable tool when determining the residual stress inside the coating before and after irradiation [20]. However, it is important to note that the calculations become more difficult if the strain values in the normal direction of the surface plane are not zero.…”

Section: X-ray Diffraction (Xrd)mentioning

confidence: 99%

“…In addition to calculations performed on the basis of the stress measurements using XRD, it is recommended that irradiation swelling of the coating and substrate be verified by calculating the swelling on the bases of TEM imaging techniques, as shown in Figure 14 [20]. EFTEM can be used to calculate the thickness of the TEM lamella, and the swelling can be calculated using image analysis software.…”

Section: Irradiation Swellingmentioning

confidence: 99%

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Development of Standardized Property Requirements, Measurement Methods, and Reporting Guidance for Coatings

Gräning¹,

Sweet²,

Mouche³

et al. 2021

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“…Corrosion-resistant coatings processed using industrial technologies, such as physical vapor deposition (PVD), CVD, electrolytic deposition, and vacuum plasma spraying (VPS) have been researched [37][38][39][40][41][42][43][44][45][46][47][48][49][50][51]. Metals (such as Cr [37][38][39][40][41][42][43][44][45][46][47][48][49], Zr [37,47] and Ti [47][48][49][50]), metal-doped SiC (such as Ti-doped and Zr-doped SiC [51]) and metal nitrides (such as CrN [37][38][39][40][41][42][43], ZrN [39,40], and TiN [37,[39][40][41][42]…”

Section: Introductionmentioning

confidence: 99%

Radiation Effect in Ti-Cr Multilayer-Coated Silicon Carbide under Silicon Ion Irradiation up to 3 dpa

et al. 2022

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Replacement of conventional Zircaloy fuel cladding with silicon carbide (SiC) fuel cladding is expected to significantly decrease the amount of hydrogen generated from fuel claddings by the reaction with steam during severe accidents. One of their critical issues addressed regarding practical application has been hydrothermal corrosion. Thus, the corrosion resistant coating technology using a Ti-Cr multilayer was developed to suppress silica dissolution from SiC fuel cladding into reactor coolant under normal operation. The effect of radiation on adhesion of the coating to SiC substrate and its microstructure characteristics were investigated following Si ion irradiation at 573 K up to 3 dpa for SiC. Measurement of swelling in pure Ti, pure Cr and SiC revealed that the maximum inner stress attributed to the swelling difference was generated between the coating and SiC substrate by irradiation of 1 dpa. No delamination and cracking were observed in cross-sectional specimens of the coated SiC irradiated up to 3 dpa. According to analyses using transmission electron microscopy, large void formation and cascade mixing due to irradiation were not observed in the coating. The swelling in the coating at 573 K was presumed to be caused by another mechanism during radiation such as point defects rather than void formation.

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Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding

Cited by 40 publications

References 53 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

Development of Standardized Property Requirements, Measurement Methods, and Reporting Guidance for Coatings

Radiation Effect in Ti-Cr Multilayer-Coated Silicon Carbide under Silicon Ion Irradiation up to 3 dpa

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