Effects of Titanium and Silicon on the Swelling Behavior of 15–15Ti Steels by Heavy-Ion Beam Irradiation

Du, Aibing; Feng, Wei; Ma, Hailiang; Tian, Liang; Yuan, Daqing; Fan, Ping; Zhang, Qiao‐Li

doi:10.1007/s40195-017-0581-8

Cited by 12 publications

(11 citation statements)

References 15 publications

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“…To date, a number of studies on the IASCC have been reported. Studies showed that the radiation-induced microstructure is one of the key factors leading to IASCC of the steel [5][6][7][8][9][10][11][12][13][14][15]. Irradiation produces high density of defect clusters such as dislocation loops and cavities in the steels.…”

Section: Introductionmentioning

confidence: 99%

Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water

Deng

Han

Peng

et al. 2020

Acta Metall. Sin. (Engl. Lett.)

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Corrosion behavior and mechanism of irradiated 304 nuclear grade stainless steel were studied in simulated pressurized water reactor primary water. The microstructure of the oxide formed on the steel irradiated to different doses over an exposure period range of 25-1500 h was analyzed and compared. It was found that the general and intergranular corrosion rates of the steel were increased with irradiation dose, in correspondence with an evolution of the general oxide and the oxide formed at the grain boundary. Correlation of the oxide evolution with the corrosion kinetics and mechanism has been discussed in detail.

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Section: Introductionmentioning

confidence: 99%

Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water

Deng

Han

Peng

et al. 2020

Acta Metall. Sin. (Engl. Lett.)

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“…Cavity-denuded regions can be observed near regions of damage peak [18]. In order to compensate for the swelling suppression of extra interstitials, the implantation of insoluble helium before heavy-ion irradiation was frequently used to enhance cavity nucleation [11,[19][20][21]. However, the role of helium, particularly its concentration, is complicated in the evolution of swelling [22][23][24][25][26][27][28][29][30][31][32].…”

Section: Introductionmentioning

confidence: 99%

Cavity Swelling of 15-15Ti Steel at High Doses by Ion Irradiation

Liu,

Ma,

Fan

et al. 2024

Materials

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The titanium-stabilized austenitic stainless steel Fe-15Cr-15Ni, which shows enhanced resistance to irradiation swelling compared with more traditional 316Ti, has been selected as a core material for fast reactors. Data on the evolution of irradiation swelling in 15-15Ti steels at very high doses, which cannot be easily achieved by neutron irradiation, are still lacking. In this paper, the swelling behavior of the titanium-modified austenitic stainless steel 15-15Ti was investigated by pre-implantation of He at room temperature followed by Ni-ion irradiation at 580 °C to peak doses of 120, 240 and 400 dpa. Relatively small cavities were observed in the zone of helium implantation, while large cavities appeared in the region near the damage peak. A correction formula for the dpa curve was proposed and applied to samples with large swelling. It was found that the steady-state swelling rate of 15-15Ti remains at ~1%/dpa even at high doses. By comparing the swelling data of the helium-implanted and helium-free regions at same doses, 70 dpa and 122 dpa, the suppression of swelling by excessive helium can be deduced at such doses.

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“…Many researchers have devoted their efforts to overcoming the problems of swelling and embrittlement in austenitic steels. One of the practicable proposals is introducing precipitates within the matrix as trapping centers for He, which has been proven feasible to improve swelling and He embrittlement in materials [23][24][25][26][27][28][29][30][31][32][33][34].…”

Section: Introductionmentioning

confidence: 99%

“…Previous experimental works showed that TiC precipitates in austenitic steels is efficient for trapping He due to their finely dispersed distributions in the matrix, so that the precipitates can reduce the He accumulates at grain boundaries, and TiC precipitates is also supposed to pin the dislocation. As a result, the addition of titanium is beneficial in reducing the sensitivity of irradiation temperature to high-temperature ductility of materials [23][24][25][26][27]. It was found that the interface of phosphide particles and matrix serves as a site for the nucleation of a fine dispersion of He bubbles, and phosphorus increases the diffusivity of matrix solvent atoms, reducing the vacancy supersaturation during irradiation [28][29][30].…”

Section: Introductionmentioning

confidence: 99%

First-principles study on the solute-induced low diffusion and self-trapping of helium in fcc iron

Rao,

Hu,

Ouyang

et al. 2022

Preprint

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The addition of alloying elements plays an essential role in helium (He) behaviours produced by transmutation in metal alloys. Effects of solutes (Ni, Cr, Ti, P, Si, C) on the behaviours of He and He-He pair in face-centred cube (fcc) iron have been investigated using first-principles calculations based on density functional theory (DFT). For the interactions of solutes and He, we found that Ti, P, Si, and C attracts He is more potent than Ni and Cr in fcc iron. We have determined the most stable configuration for the He-He pair, which is the He sub -Hetetra pair with a binding energy of 1.60 eV. In considering the effect of solutes on the stability of the He-He pair, we have proposed a unique definition of binding energy. By applying the definition, we suggest that Ti and P could weaken He self-trapping, and Cr and C are beneficial for He self-trapping, while Ni is similar to the matrix Fe itself. For the diffusion of He, which is the necessary process of forming the He bubble, we determined that the most stable interstitial He is in a tetrahedral site and could migrate with the energy barrier of 0.16 eV in pure fcc iron. We further found that Ti and Si can increase the barrier to 0.18 and 0.20 eV; on the contrary, Cr and P decrease the barrier to 0.10 and 0.06 eV, respectively. Summarizing the calculations, we conclude that Ti decreases while Cr increases the diffusion and self-trapping of He in fcc iron.

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Effects of Titanium and Silicon on the Swelling Behavior of 15–15Ti Steels by Heavy-Ion Beam Irradiation

Cited by 12 publications

References 15 publications

Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water

Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water

Cavity Swelling of 15-15Ti Steel at High Doses by Ion Irradiation

First-principles study on the solute-induced low diffusion and self-trapping of helium in fcc iron

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