Nanocluster evolution and mechanical properties of ion irradiated T91 ferritic-martensitic steel

Davis, Thomas P.; Auger, M.A.; Hofer, Christina; Bagot, Paul A.J.; Moody, Michael P.; Armstrong, David E.J.

doi:10.1016/j.jnucmat.2021.152842

Cited by 7 publications

(4 citation statements)

References 68 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Moreover, He atoms can be trapped by different kinds of boundaries (grain/subgrain, martensite pocket/block/lath, and precipitates, etc.) [18], dislocations and other sinks in the F/M steel to form a He cluster [19,20]. The formed He cluster continuously absorbs external He atoms, eventually leading to the generation of a high density of He bubbles, as observed by transmission electron microscopy (TEM) [21].…”

Section: Introductionmentioning

confidence: 99%

Microstructure Characterization and Hardening Evaluation of Ferrite/Martensitic Steels Induced by He2+ Irradiation

Zhang,

Yang,

Xie

et al. 2023

Crystals

View full text Add to dashboard Cite

Two ferrite/martensitic (F/M) steels with different Si concentrations (0 and 0.4 wt.%) were irradiated by 250 keV He2+ ions with different fluences of 2 × 1016 ions/cm2 and 1 × 1017 ions/cm2. Transmission electron microscopy and a nanoindenter were employed to investigate their microstructure evolution and irradiation hardening effects induced by high-energy He2+ ions. A large number of He bubbles formed in the Si-free and Si-containing F/M steels, which preferentially nucleated and grew at the lath and phase boundaries. Owing to the inhibiting effect of Si addition on He bubble growth, the He bubbles in the Si-containing sample exhibited smaller size and higher density at the same He2+ fluence. Nanoindenter measurement revealed that typical irradiation hardening was observed in the F/M steel, and 1/2<111> and <100> type dislocation loops formed by He2+ irradiation was recognized as the dominant mechanism. The addition of Si induced an increase in the number density of dislocation loops, leading to the exacerbation of the irradiation hardening, and the results are basically in agreement with the theoretical analysis based on the dispersion barrier hardening (DBH) and Friedel–Kroupa–Hirsch (FKH) models.

show abstract

Section: Introductionmentioning

confidence: 99%

Microstructure Characterization and Hardening Evaluation of Ferrite/Martensitic Steels Induced by He2+ Irradiation

Zhang,

Yang,

Xie

et al. 2023

Crystals

View full text Add to dashboard Cite

show abstract

“…Irradiation-induced growth, hightemperature phase transition, high-temperature oxidation, and strong corrosion from liquid heavy metals [8][9][10][11] are major challenges Zr-based alloys are facing. Other firstwall materials, such as austenitic stainless steel, and Tiema Steel, are also vulnerable to plasma corrosion [12,13], irradiation swelling [14,15] and high-temperature stability [16][17][18]. Additionally, oxide dispersion strengthening (ODS) has also been employed to improve the creep resistance and radiation resistance of steel [19][20][21], but still not mature enough for mass production.…”

Section: Introductionmentioning

confidence: 99%

Study on Microstructure and High Temperature Stability of WTaVTiZrx Refractory High Entropy Alloy Prepared by Laser Cladding

Ding,

Wang,

Zhang

et al. 2024

Entropy

View full text Add to dashboard Cite

The extremely harsh environment of the high temperature plasma imposes strict requirements on the construction materials of the first wall in a fusion reactor. In this work, a refractory alloy system, WTaVTiZrx, with low activation and high entropy, was theoretically designed based on semi-empirical formula and produced using a laser cladding method. The effects of Zr proportions on the metallographic microstructure, phase composition, and alloy chemistry of a high-entropy alloy cladding layer were investigated using a metallographic microscope, XRD (X-ray diffraction), SEM (scanning electron microscope), and EDS (energy dispersive spectrometer), respectively. The high-entropy alloys have a single-phase BCC structure, and the cladding layers exhibit a typical dendritic microstructure feature. The evolution of microstructure and mechanical properties of the high-entropy alloys, with respect to annealing temperature, was studied to reveal the performance stability of the alloy at a high temperature. The microstructure of the annealed samples at 900 °C for 5–10 h did not show significant changes compared to the as-cast samples, and the microhardness increased to 988.52 HV, which was higher than that of the as-cast samples (725.08 HV). When annealed at 1100 °C for 5 h, the microstructure remained unchanged, and the microhardness increased. However, after annealing for 10 h, black substances appeared in the microstructure, and the microhardness decreased, but it was still higher than the matrix. When annealed at 1200 °C for 5–10 h, the microhardness did not increase significantly compared to the as-cast samples, and after annealing for 10 h, the microhardness was even lower than that of the as-cast samples. The phase of the high entropy alloy did not change significantly after high-temperature annealing, indicating good phase stability at high temperatures. After annealing for 10 h, the microhardness was lower than that of the as-cast samples. The phase of the high entropy alloy remained unchanged after high-temperature annealing, demonstrating good phase stability at high temperatures.

show abstract

“…Among them, ferritic/martensitic steel and austenitic stainless steel have the advantages of economy and high mechanical strength, but their corrosion in SCW need to be further investigated (Zhang et al, 2012;Davis et al, 2021;Tsisar et al, 2020). The corrosion behaviors of ferritic/martensitic steel and austenitic stainless steel in SCW have been extensively studied, and the oxidation layers formed were generally reported to have a duplex structure (Chen et al, 2020;Cai et al, 2021).…”

Section: Introductionmentioning

confidence: 99%

“…Preliminary screening and evaluation of the structural materials that have been used in LWR were carried out, and four candidates for SCWR were proposed, including ferritic/martensitic steel, austenitic stainless steel, nickel-based alloy and oxide dispersion reinforced steel (Zhang et al , 2021; Terrani, 2018; Konings et al , 2015; Zinkle et al , 2014; Hu et al , 2022). Among them, ferritic/martensitic steel and austenitic stainless steel have the advantages of economy and high mechanical strength, but their corrosion in SCW need to be further investigated (Zhang et al , 2012; Davis et al , 2021; Tsisar et al , 2020). The corrosion behaviors of ferritic/martensitic steel and austenitic stainless steel in SCW have been extensively studied, and the oxidation layers formed were generally reported to have a duplex structure (Chen et al , 2020; Cai et al , 2021).…”

Section: Introductionmentioning

confidence: 99%

Oxidation behavior of the T91 ferritic/martensitic steel and 304 austenitic stainless steel in supercritical water

An²,

Wang³

2023

ACMM

View full text Add to dashboard Cite

Purpose This study aims to report the oxidation behaviors of the T91 ferritic/martensitic steel (T91 steel) and 304 austenitic stainless steel (304 steel) in supercritical water (SCW) at 600°C. Design/methodology/approach The microstructure, elemental distribution and phase structure of the oxidation layers derived from the corrosion of the T91 steel and 304 steel were analyzed by scanning electron microscopy, Oxford Instrument X-ray spectroscopy, electron scattered diffraction and transmission electron microscopy. Findings The oxidation layers on the T91 steel and 304 steel have duplex structure. The two steels all suffer internal oxidation, and the phase of the internal oxidation layers are indexed as Fe-Cr spinel, although their morphologies are different. The formation of a continuous Cr-rich layer is not detected because of the relatively low Cr content of the steels, which is attributed to the corrosion property. Originality/value The accelerated corrosion and corrosion mechanism of the T91 steel and 304 steel with low Cr occurring in SCW at 600°C was clarified.

show abstract

Nanocluster evolution and mechanical properties of ion irradiated T91 ferritic-martensitic steel

Cited by 7 publications

References 68 publications

Microstructure Characterization and Hardening Evaluation of Ferrite/Martensitic Steels Induced by He2+ Irradiation

Microstructure Characterization and Hardening Evaluation of Ferrite/Martensitic Steels Induced by He2+ Irradiation

Study on Microstructure and High Temperature Stability of WTaVTiZrx Refractory High Entropy Alloy Prepared by Laser Cladding

Oxidation behavior of the T91 ferritic/martensitic steel and 304 austenitic stainless steel in supercritical water

Contact Info

Product

Resources

About