Swelling resistance of an austenitic stainless steel with uniformly distributed nanosized NbC precipitates under heavy ion irradiation

Shin, Ji Ho; Kong, Byeong Seo; Jeong, Chaewon; Eom, Hyun Joon; Jang, Changheui; Almousa, Nouf; Woller, K.; Short, Michael P.

doi:10.1016/j.jnucmat.2022.153678

Cited by 7 publications

(2 citation statements)

References 59 publications

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“…Among them, the development of Super 304H is a typical example. The Super 304H steel was developed from Type 304H steel by adding 3% Cu, 0.3% Nb, and 0.1% N. Generally, the Nb combining with C and N generates the Nb(C,N) (MX) phase in FCC-typed steel [4][5][6]. Part of MX phase are nanoscale particles after solid solution treatment which contributes to the fine grain of Super 304H.…”

Section: Introductionmentioning

confidence: 99%

Strengthening and Embrittling Mechanism of Super 304H Steel during Long-Term Aging at 650 °C

Wu,

Chai,

Liu

et al. 2024

Materials

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Super 304H has been a crucial material for ultra-supercritical boilers. However, the relationship between microstructure evolution, strengthening mechanism, and embrittling behavior during long-term aging was lacking investigation. This investigation aimed to reveal the strengthening and embrittling mechanism from precipitates in Super 304H. The results showed that the hardness increment came from the grain boundary’s M23C6 (GB’s M23C6) and intragranular nano Cu-rich particles. After being aged for 5000 h, the GB’s M23C6 and nano Cu-rich particles provided a hardness increment of approximately 10 HV and 30 HV, respectively. The impact toughness gradually decreased from 213 J/cm2 to 161 J/cm2 with the extending aging time. For the aged Super 304H, the GB’s M23C6 provided a higher cracking source. In addition, the nano Cu-rich particle restricted the twin-induced plastic deformation of austenitic grain and depressed the absorbed energy from austenitic grain deformation.

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Section: Introductionmentioning

confidence: 99%

Strengthening and Embrittling Mechanism of Super 304H Steel during Long-Term Aging at 650 °C

Wu,

Chai,

Liu

et al. 2024

Materials

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“…Austenitic stainless steel is used in some fast and gas-cooled reactors. Although austenitic stainless steel (FCC) has a low thermal conductivity and its swelling resistance [16] and yield strength need to be improved. Ferritic/martensitic steel (RAFM) with a BCC structure has good swelling resistance; however, the high-temperature irradiation environment instability leads to a sharp decline in mechanical properties due to the negative effect of impurities in RAFM [17].…”

Section: Introductionmentioning

confidence: 99%

A Review of Irradiation-Tolerant Refractory High-Entropy Alloys

Wang,

Yang,

Shu

et al. 2023

Metals

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Along with the globalization of environmental problems and the rapid development of the field of nuclear technologies, the severe irradiation damage of materials has become a big issue, restricting the development of advanced nuclear reactor systems. Refractory high-entropy alloys (RHEAs) have the characteristics of a complex composition, a short-range order, and lattice distortion and possess a high phase stability, outstanding mechanical properties, and excellent irradiation resistance at elevated temperatures; thus, they are expected to be promising candidates for advanced nuclear reactors. This review summarizes the design, preparation, and irradiation resistance of irradiation-tolerant RHEAs. It encompasses a comprehensive analysis of various aspects, including the evolution of defects, changes in microstructure, and the degradation in properties. Furthermore, the challenges and insufficiently researched areas regarding these alloys are identified and discussed. Building on this foundation, the review also provides a forward-looking perspective, outlining potential avenues for future research.

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Evolution of precipitate and its effect on dislocation loops during in-situ He+ irradiation and annealing

Huang,

Zhong,

Cao

et al. 2025

International Journal of Refractory Metals and Hard Materials

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Swelling resistance of an austenitic stainless steel with uniformly distributed nanosized NbC precipitates under heavy ion irradiation

Cited by 7 publications

References 59 publications

Strengthening and Embrittling Mechanism of Super 304H Steel during Long-Term Aging at 650 °C

Strengthening and Embrittling Mechanism of Super 304H Steel during Long-Term Aging at 650 °C

A Review of Irradiation-Tolerant Refractory High-Entropy Alloys

Evolution of precipitate and its effect on dislocation loops during in-situ He+ irradiation and annealing

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