Development of oxide dispersion strengthened vanadium alloy and its properties

Shibayama, Tamaki; Yamagata, Ichiro; Kurishita, Hiroaki; Kayano, Hideo

doi:10.1016/s0022-3115(96)00469-2

Cited by 14 publications

(4 citation statements)

References 3 publications

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“…In this context, oxide dispersion strengthening technology has received increasing attention as a method for further enhancing the high-temperature performance of alloys [2,3]. Studies have shown that it can significantly enhance the operating temperature, mechanical properties, and radiation resistance of vanadium alloy, leading to an extension of service life [4][5][6]. Due to the special environment of liquid Li in which vanadium alloys will operate, and the greater affinity of vanadium alloys for C compared to O in liquid Li environments, carbides are more suitable for dispersion strengthening of vanadium alloys [7][8][9].…”

Section: Introductionmentioning

confidence: 99%

Irradiation Hardening and Microstructure Study of MAX-Phase-Dispersion-Strengthened Vanadium Alloy under Self-Ion Irradiation

Zhao,

Zheng,

Wei

et al. 2024

Metals

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V-4Cr-4Ti alloy is one of the candidate structural materials for future fusion reactors due to its desirable characteristics. In our previous research, MAX-phase-dispersion-strengthened vanadium alloy (V-4Cr-4Ti-1.5Y-0.3Ti3SiC2), prepared through mechanical alloying, showed excellent thermal stability and creep resistance and was expected to have good radiation resistance. This study investigates the effects of 2.5 MeV V2+ ion irradiation on V-4Cr-4Ti-1.5Y-0.3Ti3SiC2 and V-4Cr-4Ti alloys at 500 °C, with peak damage of 0.8, 3.5, and 6.1 dpa. Transmission electron microscopy and nanoindentation were used to examine the changes in microstructure and hardness before and after irradiation. The microscopic analysis reveals that dispersed nanoparticles maintained good stability under irradiation. Defect clusters grow with increasing irradiation doses in both materials. The nanoindentation results show that V-4Cr-4Ti-1.5Y-0.3Ti3SiC2 has higher initial hardness and lower irradiation hardening, indicating better resistance to radiation hardening than V-4Cr-4Ti. This research serves as a valuable reference for the assessment of the irradiation resistance of Ti3SiC2-dispersion-strengthened V-4Cr-4Ti alloy.

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Section: Introductionmentioning

confidence: 99%

Irradiation Hardening and Microstructure Study of MAX-Phase-Dispersion-Strengthened Vanadium Alloy under Self-Ion Irradiation

Zhao,

Zheng,

Wei

et al. 2024

Metals

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“…In vanadium alloys, the addition of Cr would improve the high temperature mechanical performance of the vanadium alloys and the addition of Ti would suppress void swelling under neutron irradiation [1]- [6]. However, it is known that the interstitial impurities of carbon, oxygen, and nitrogen (C, O, N) of a V-4Cr-4Ti alloy also play an important role in radiation effects such as microstructural changes, irradiation hardening, and embitterment [7]- [10]. Recently, there are a large number of reports about how to change Ti(C, O, N) precipitates to improve properties of vanadium-based alloys.…”

Section: Introductionmentioning

confidence: 99%

First-Principles Study of Segregation Behavior of Cr/Ti/Y at Grain Boundary in Vanadium

Lee¹,

Yi²,

Bee³

2018

IJMMM

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Abstract-The atomic arrangement and segregation behavior of Ti, Cr, and Y in Σ3 (111) grain boundary of vanadium was performed to illustrate by first-principle calculation. The analyses on the binding energies and geometric positions show that Cr atom is more stable than Ti or Y atom both in the bulk and grain boundary, and Y atom would push away the surrounding V atoms. The computations of segregation energies show that Cr/Y atom segregates at the grain boundary, while Ti atom prefers to stay in bulk V rather than in grain boundary. Furthermore, it is found that Ti/Y atom has a strong driving force to surface segregation. The grain boundary energies calculations and the work of separation and the electron properties show that the segregated Cr can strengthen the grain boundary, whereas segregated Y has the strong tendency to decrease crystallite size.

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“…MA-treated vanadium powder, however, has large affinity with interstitial impurities such as oxygen and nitrogen, yielding a lack of ductility of vanadium alloys produced by MA without irradiation. 1,11,12) One of our authors had successfully developed vanadium alloys having ultra-fine grains with dispersed particles containing extremely little interstitial impurities by using MA method. 13) Threepoint bend impact tests showed that the alloys exhibited good ductility even at 77 K. 13) To the authors' knowledge, no work has focused on the microstructural evolutions of such alloys after irradiation.…”

Section: Introductionmentioning

confidence: 99%

Effect of Fast Neutron Irradiation on the Microstructure in Particle Dispersed Ultra-fine Grained V-Y Alloys

et al. 2004

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An alloy having ultra-fine grains with dispersed particles is expected to have the resistance of irradiation embrittlement. We examine the microstructures of V-1.6 and 2.6Y alloys, having ultra-fine grains with dispersed particles, after neutron irradiation at temperatures between 290 and 800 C. The grain size was the level of a few hundreds of nanometers, and the size in diameter of V-2.6Y alloy was much smaller than that of V-1.6Y alloy, where the irradiation did not change the size. The number density of particles in V-2.6Y alloy was higher than that in V-1.6Y alloy. Voids were formed only at 290 C, where the number density of voids in V-2.6Y alloy was smaller than that in V-1.6Y alloy. The void formation was efficiently suppressed due to fine-grains and dispersed particles.

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Development of oxide dispersion strengthened vanadium alloy and its properties

Cited by 14 publications

References 3 publications

Irradiation Hardening and Microstructure Study of MAX-Phase-Dispersion-Strengthened Vanadium Alloy under Self-Ion Irradiation

Irradiation Hardening and Microstructure Study of MAX-Phase-Dispersion-Strengthened Vanadium Alloy under Self-Ion Irradiation

First-Principles Study of Segregation Behavior of Cr/Ti/Y at Grain Boundary in Vanadium

Effect of Fast Neutron Irradiation on the Microstructure in Particle Dispersed Ultra-fine Grained V-Y Alloys

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