Effect of yttrium content on microstructure and irradiation behavior of V-4Cr-4Ti-xY alloys

Luo, Hao; Luo, Fengfeng; Chen, Yiheng; Wang, Jiawei; Liu, Qiu-Xiang; Li, Fang; Xie, Ziyang; Lin, Wenbin; Guo, Liping

doi:10.1016/j.jnucmat.2021.153480

Cited by 13 publications

(7 citation statements)

References 47 publications

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“…Figure 2 showed SRIM simulation calculation of 2.7 MeV Si 2+ ion implantation into pure tungsten that reached peak damage of 100 dpa using the model of Ion Distribution and Quick Calculation of Damage [ 30 ], and displacement energy of 90 eV [ 31 ], a total of 100,000 ions simulation were performed. The dose rate at different depths could be simulated by dividing the dose by the total irradiation time, as a result the dose rate corresponding to the damage peak was 1.2 × 10 −3 dpa/s.…”

Section: Methodsmentioning

confidence: 99%

The Effect of Rhenium Content on Microstructural Changes and Irradiated Hardening in W-Re Alloy under High-Dose Ion Irradiation

Luo

Liu

et al. 2023

Nanomaterials

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An amount of 100 dpa Si2+ irradiation was used to study the effect of transmutation rhenium content on irradiated microscopic defects and hardening in W-xRe (x = 0, 1, 3, 5 and 10 wt.%) alloys at 550 °C. The increase in Re content could significantly refine the grain in the W-xRe alloys, and no obvious surface topography change could be found after high-dose irradiation via the scanning electron microscope (SEM). The micro defects induced by high-dose irradiation in W and W-3Re alloys were observed using a transmission electron microscope (TEM). Dislocation loops with a size larger than 10 nm could be found in both W and W-3Re alloy, but the distribution of them was different. The distribution of the dislocation loops was more uniform in pure W, while they seemed to be clustered around some locations in W-3Re alloy. Voids (~2.4 nm) were observed in W-3Re alloy, while no void was investigated in W. High-dose irradiation induced obvious hardening with the hardening rate between 75% and 155% in all W-xRe alloys, but W-3Re alloy had the lowest hardening rate (75%). The main reasons might be related to the smallest grain size in W-3Re alloy, which suppressed the formation of defect clusters and induced smaller hardening than that in other samples.

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Section: Methodsmentioning

confidence: 99%

The Effect of Rhenium Content on Microstructural Changes and Irradiated Hardening in W-Re Alloy under High-Dose Ion Irradiation

Luo

Liu

et al. 2023

Nanomaterials

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“…It is evident that V-4Cr-4Ti-1.5Y-0.3Ti 3 SiC 2 exhibits superior resistance to radiation hardening compared to V-4Cr-4Ti. In the study of Luo et al [19], the initial hardness of V-4Cr-4Ti prepared using the arc melting method was approximately 2.3 GPa, and the hardening value of V-4Cr-4Ti was approximately 9.8 GPa after being irradiated to 35 dpa with Fe 2+ ions at 550 • C. The results of their study are comparable to our experimental results, indicating that V-4Cr-4Ti reaches a hardening saturation value of approximately 10 GPa under ion irradiation at around 500 • C.…”

Section: Effect Of Irradiation Dose On Hardnessmentioning

confidence: 97%

“…Y is also added to reduce impurity elements such as O in the matrix [17,18]. Furthermore, the addition of Y can also enhance mechanical performance and reduce irradiation hardening [19][20][21]. Prior research reveals that a V-4Cr-4Ti alloy with "Y + Ti 3 SiC 2 " has a higher hardness after annealing at various high temperatures when compared to an alloy with "Y + TiC" and "Y + SiC", demonstrating the exceptional thermal stability of this dispersion strengthening phase [22].…”

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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“…Element Y has been used to enhance the oxidation resistance properties of a number of superalloys [13][14][15]. Moreover, Y can inhibit grain boundary migration and inhibit grain growth [15,16], and it has been widely applied to refine the microstructure of material [17][18][19]. Adding 0.3 wt% Y has been found to improve the tensile properties of the material [19].…”

Section: Introductionmentioning

confidence: 99%

“…Adding 0.3 wt% Y has been found to improve the tensile properties of the material [19]. Y has also been found to inhibit cavity swelling [16]. However, the effect of Y on the dislocation loop of FeCrAl alloy at high temperature has not been reported.…”

Section: Introductionmentioning

confidence: 99%

Ion Irradiation Defects and Hardening in FeCrAl Alloy

Long

Guo

et al. 2022

Metals

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The self-ion irradiation experiments of FeCrAl and Y−FeCrAl alloys are carried out at 330 °C to 1–10 displacements per atom (dpa). The formation of dislocation loops in these alloys is investigated by transmission electron microscopy (TEM) and nano-indentation tests are used to assess the irradiation hardening. A large number of dislocation loops are formed after irradiation, and dislocation network gradually develops above 2.5 dpa. The average size of dislocation loops increases while the number density decreases when the dose was increased. In comparison to a/2<111> dislocation loops, a<100> dislocation loops have a larger average size and higher proportion. Higher temperatures and dose rate can increase the proportion of a<100> dislocation loops. As the dose is increasing, irradiation hardening increases. The addition of yttrium increases the proportion of a<100> dislocation loops and reduces the irradiation hardening due to the high binding energy between yttrium atom and vacancy.

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Effect of yttrium content on microstructure and irradiation behavior of V-4Cr-4Ti-xY alloys

Cited by 13 publications

References 47 publications

The Effect of Rhenium Content on Microstructural Changes and Irradiated Hardening in W-Re Alloy under High-Dose Ion Irradiation

The Effect of Rhenium Content on Microstructural Changes and Irradiated Hardening in W-Re Alloy under High-Dose Ion Irradiation

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

Ion Irradiation Defects and Hardening in FeCrAl Alloy

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