On the thermal stability of a 9Cr-ODS steel aged at 700 °C up to 10000 h - Mechanical properties and microstructure

Zheng, Pengfei; Li, Yanfen; Zhang, Jiarong; Shen, Jingjie; Nagasaka, Tetsuya; Muroga, T.; Abe, Hiroaki

doi:10.1016/j.msea.2020.139292

Cited by 25 publications

(4 citation statements)

References 26 publications

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“…The material still contained small amounts of Mn or Al oxides, which were introduced by the elemental powder's high affinity to oxygen [67,70] and also resulted in the formation of micropores. These oxides are stable at the performed annealing temperatures and may coarsen only at higher temperature [73] or longer annealing [74]. Therefore, O did not go into solution by the heat treatment and did not influence the phase stability or microstructure constitution.…”

Section: Materials and Processingmentioning

confidence: 99%

Thermodynamics, microstructure evolution and mechanical properties of Al- and C-added CoFeMnNi multi-principal element alloys

Kies

Noori²,

Ewald³

et al. 2022

Materials & Design

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Section: Materials and Processingmentioning

confidence: 99%

Thermodynamics, microstructure evolution and mechanical properties of Al- and C-added CoFeMnNi multi-principal element alloys

Kies

Noori²,

Ewald³

et al. 2022

Materials & Design

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“…Oxide dispersion-strengthened (ODS) steels are one of the promising candidates for fuel cladding materials because of their outstanding high-temperature properties and remarkable tolerance to irradiation damage [4][5][6][7][8][9]. The corrosion behavior of various ODS steels has been tested and certain ODS steels showed good corrosion resistance owing to the formation of compact oxide layers on the surface.…”

Section: Introductionmentioning

confidence: 99%

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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“…A series of ODS steels has been developed and tested to be used as the fusion blanket structural material (Zinkle et al, 2017) or in liquid lead-bismuth eutectic (LBE) or lead cooled reactors (Kimura et al, 2011;Song et al, 2019). M 23 C 6 carbides, which commonly appear in ferritic/martensitic ODS steels and pin the grain boundaries, would be unstable in the high-temperature environment (Zheng et al, 2020), setting a limitation on the working temperature for such ODS steels. A novel MX-ODS steel with extremely low carbon content was developed (RUI, 2022) to eliminate M 23 C 6 carbides and take the advantage of MX (M = Ta/ V, X = C/N) precipitates as second-phase strengthening (Tan et al, 2016).…”

Section: Introductionmentioning

confidence: 99%

Effects of Fe self-ion irradiation on a low carbon MX-ODS steel at 550°C

Yun

et al. 2023

Front. Energy Res.

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Oxide Dispersion Strengthened (ODS) steels with nano-scale oxides have become one of the candidate materials used in advanced nuclear reactor systems. A novel MX-ODS steel with extremely low carbon content was irradiated with 3 MeV Fe ions at 550°C up to peak damage of 70 dpa. The steel contains uniformly distributed Y2O3 nano-precipitates with an average size of 3.5 nm and a number density of 5 × 1022/m3. A V-rich shell was found surrounding the core of Y, O, and Si at some particles. Two types of large precipitates, Y-Ta-Si oxides, and VN, were observed in the steel instead of carbides. Voids of very small size are present due to irradiation and the calculated void swelling was only 0.004%, suggesting good irradiation tolerance of the MX-ODS steel in this study. Fine and dense oxide nano-precipitates and their shell-core structure remained stable while the shape of large precipitates changed after irradiation.

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On the thermal stability of a 9Cr-ODS steel aged at 700 °C up to 10000 h - Mechanical properties and microstructure

Cited by 25 publications

References 26 publications

Thermodynamics, microstructure evolution and mechanical properties of Al- and C-added CoFeMnNi multi-principal element alloys

Thermodynamics, microstructure evolution and mechanical properties of Al- and C-added CoFeMnNi multi-principal element alloys

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

Effects of Fe self-ion irradiation on a low carbon MX-ODS steel at 550°C

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