Corrosion behaviour of oxide dispersion strengthened iron‐chromium steels in liquid lead at 973 K

Ricci, E.; Giuranno, Donatella; Canu, Giovanna; Amore, S.; Novaković, R.

doi:10.1002/maco.201709995

Cited by 8 publications

(2 citation statements)

References 65 publications

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“…Such results were unexpected since irradiation is regarded as having adverse effects on the lead/LBE corrosion performance of materials. The oxides in the irradiated specimen contained an inner layer of spinel and an outer layer of magnetite, which has been widely reported in oxygen-saturated Pb or LBE [29][30][31][32][33][34][35]. In the as-received specimen after corrosion, a large area suffered from Pb attack and dissolution, with oxides formed in part of the areas; however, they were not protective.…”

Section: Comparison Of the As-received Specimen And The Irradiated Sp...mentioning

confidence: 84%

The Effects of Irradiation on the Improvement in Oxidation Behavior of MX-ODS Steel in Liquid Pb

Xu,

Xie,

Qiu

et al. 2024

Nanomaterials

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Lead-cooled fast reactors exhibit strong inherent safety performance and good economic features, while material degradation due to corrosion and irradiation is still challenging. Oxide dispersion-strengthened steels are one of the promising candidates for fuel cladding materials. The effects of both irradiation and corrosion on ODS steel need to be further studied. In this work, MX-ODS steel was irradiated by Fe ions at 500 °C up to 46 dpa. Later, the as-received specimen and the irradiated specimen were used to conduct corrosion tests in oxygen-saturated Pb at 550 °C for 1 h. In the as-received specimen, discontinuous oxides penetrated by Pb and Pb in contact with steel matrix were observed, demonstrating unsatisfactory corrosion resistance of the material. However, in the irradiated specimen after corrosion experiment, a protective oxide layer formed and prevented Pb attack. The oxidation behavior differences between the two specimens can be attributed to the defects produced by irradiation and the structural discrepancy in oxides caused by the formation process. A possible mechanism of irradiation on the corrosion is discussed. In the as-received specimen, Fe atoms loss led to voids in the oxides, and lead penetrated the oxides through these voids. In the irradiated specimen, defects left by previous irradiation helped to form a more uniform oxide layer. The adhesive outer magnetite oxide and the Fe ions generated from where grain boundary oxidation developed retarded the presence of voids and made the oxide layer protective.

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Section: Comparison Of the As-received Specimen And The Irradiated Sp...mentioning

confidence: 84%

The Effects of Irradiation on the Improvement in Oxidation Behavior of MX-ODS Steel in Liquid Pb

Xu,

Xie,

Qiu

et al. 2024

Nanomaterials

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“…Moreover, the high Cr contents of T91 F/M and ODS ferritic steels result in the formation of more protective Cr-based oxide scales as compared to steels with lower Cr contents. The better protectiveness of Cr-based oxide scales is reflected in the longer incubation times needed for the onset of dissolution corrosion [101,225,241].…”

Section: The Role Of Steel Chemical Compositionmentioning

confidence: 99%

Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors

Gong

Short

Auger

et al. 2022

Progress in Materials Science

191

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Corrosion properties of Ti₃SiC₂ and Ti₃AlC₂ in static liquid lead–bismuth eutectic at 500°C

Zhu

Liu

Chang

et al. 2021

Materials & Corrosion

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For lead‐cooled fast reactors and accelerator‐driven subcritical systems, the surface corrosion behavior of candidate structural materials in lead–bismuth eutectic (LBE) is a key issue, which determines whether the material is applicable. The candidate materials of two typical MAX phases, Ti3SiC2 and Ti3AlC2, were immersed in static LBE with saturated oxygen concentration at 500°C for up to 3000 h. The corrosion behaviors of Ti3SiC2 and Ti3AlC2 were analyzed by scanning electron microscope, energy‐dispersive X‐ray, X‐ray diffraction, and Raman spectra. The experimental results showed that elements interdiffusion between LBE and sample matrix occurred on both Ti3SiC2 and Ti3AlC2 surfaces, which led to the formation of the diffusion layer. The dominant component of the diffusion layer is PbTiO3, which makes the corroded surface fragile in a stress environment. Besides, there were differences in structures of corroded sample surfaces between Ti3SiC2 and Ti3AlC2. The corrosion layer of Ti3SiC2 consisted of two layers, while only one single layer formed on Ti3AlC2 surfaces. The stable oxide layer consisting of SiO2 and TiO2 can protect Ti3SiC2 samples from further LBE corrosion and maintain the integrity of the surfaces. For Ti3AlC2 samples, it is hard to form a continuous Al2O3 protective layer, thus no stable oxide layer was detected on the corroded surfaces. Compared with Ti3AlC2, Ti3SiC2 showed better corrosion resistance in LBE.

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Corrosion behaviour of oxide dispersion strengthened iron‐chromium steels in liquid lead at 973 K

Cited by 8 publications

References 65 publications

The Effects of Irradiation on the Improvement in Oxidation Behavior of MX-ODS Steel in Liquid Pb

The Effects of Irradiation on the Improvement in Oxidation Behavior of MX-ODS Steel in Liquid Pb

Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors

Corrosion properties of Ti₃SiC₂ and Ti₃AlC₂ in static liquid lead–bismuth eutectic at 500°C

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Corrosion behaviour of oxide dispersion strengthened iron‐chromium steels in liquid lead at 973 K

Cited by 8 publications

References 65 publications

The Effects of Irradiation on the Improvement in Oxidation Behavior of MX-ODS Steel in Liquid Pb

The Effects of Irradiation on the Improvement in Oxidation Behavior of MX-ODS Steel in Liquid Pb

Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors

Corrosion properties of Ti3SiC2 and Ti3AlC2 in static liquid lead–bismuth eutectic at 500°C

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Product

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Corrosion properties of Ti₃SiC₂ and Ti₃AlC₂ in static liquid lead–bismuth eutectic at 500°C