A quantitative method to determine the region not influenced by injected interstitial and surface effects during void swelling in ion-irradiated metals

Li, Yongchang; French, Aaron; Hu, Zhihan; Gabriel, Adam; Hawkins, Laura; Garner, F.А.; Shao, Lin

doi:10.1016/j.jnucmat.2022.154140

Cited by 13 publications

(7 citation statements)

References 66 publications

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“…The selection considers the fact that void swelling is frequently observed in pure Fe at temperatures around 500°C [14]. MD-obtained kinetics yields a swelling temperature range in good agreement with experimental observations, as will be shown in this study.…”

Section: Modeling Proceduressupporting

confidence: 81%

“…Combining Eqs. (12)(13)(14) for a steady state under irradiation, a quadratic equation is derived for vacancy concentration deviation from its equilibrium (∆C v = C v − C v eq ), expressed as:…”

Section: Void Nucleation Considering Irradiation For Defect Productio...mentioning

confidence: 99%

“…Among the numerous factors influencing void nucleation, the impact of impurities, especially carbon, holds significance. Recent studies indicate that a carbon concentration at ~100 atomic parts per million (appm) can alter the void distribution profile in irradiated-iron [3]. Given that carbon is a common contaminant and is often utilized as an alloying element, whether intentionally or unintentionally, it becomes imperative to investigate its effects.…”

Section: Introductionmentioning

confidence: 99%

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Effect of Carbon on Void Nucleation in Iron

Shao

2024

Preprint

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The nucleation of voids in alpha iron and the influence of carbon were investigated through a combination of rate theory and nucleation theory calculations. The steady rates of void nucleation exhibit high sensitivity to carbon. Even a seemingly negligible carbon concentration, as low as a few atomic parts per million (appm), can dramatically reduce the nucleation rates and narrow the temperature window for nucleation. This study highlights the challenges in certifying and qualifying nuclear materials for use in reactor environments. It emphasizes the necessity for precise control of impurity levels during materials processing and stringent requirements for irradiation testing, which are susceptible to contamination. Furthermore, the study provides an explanation for the significant data scattering observed in void swelling behaviors as reported in the literature.

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Section: Modeling Proceduressupporting

confidence: 81%

Section: Void Nucleation Considering Irradiation For Defect Productio...mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Effect of Carbon on Void Nucleation in Iron

Shao

2024

Preprint

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“…The high radiation tolerance of nanoscale multilayer Zr/Nb systems has been demonstrated in recent studies, including helium ion irradiation [ 17 , 18 , 19 , 20 , 21 , 22 , 23 , 24 , 25 ]. Helium atoms are produced in materials as a result of nuclear reactions (n, α) [ 26 ] and tend to accumulate in vacancies and interstitials with the formation of helium bubbles, leading to changes in the macroscopic properties of the irradiated material [ 27 , 28 , 29 , 30 , 31 , 32 , 33 ]. However, the accumulation of helium atoms at the Zr/Nb interface and their effect on the atomic and electronic structure of metals remain incompletely understood.…”

Section: Introductionmentioning

confidence: 99%

Features of Helium–Vacancy Complex Formation at the Zr/Nb Interface

Svyatkin

Laptev

2023

Materials

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A first-principles study of the atomic structure and electron density distribution at the Zr/Nb interface under the influence of helium impurities and helium–vacancy complexes was performed using the optimised Vanderbilt pseudopotential method. For the determination of the preferred positions of the helium atom, the vacancy and the helium–vacancy complex at the interface, the formation energy of the Zr-Nb-He system has been calculated. The preferred positions of the helium atoms are in the first two atomic layers of Zr at the interface, where helium–vacancy complexes form. This leads to a noticeable increase in the size of the reduced electron density areas induced by vacancies in the first Zr layers at the interface. The formation of the helium–vacancy complex reduces the size of the reduced electron density areas in the third Zr and Nb layers as well as in the Zr and Nb bulk. Vacancies in the first niobium layer near the interface attract the nearest zirconium atoms and partially replenish the electron density. This may indicate a possible self-healing of this type of defect.

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“…In the case of an increase in the operating temperature of the core, which makes it possible to achieve a higher degree of nuclear fuel burnup, the concentration of the resulting implanted helium increases, and its mobility in the damaged layer also increases [11,12]. An increase in the mobility of implanted helium as well as its low solubility can lead to an acceleration of swelling processes due to the formation of many gas-filled bubbles.…”

Section: Introductionmentioning

confidence: 99%

Study of The Gas-Swelling Mechanisms in Silicon Carbide Ceramics under High-Temperature Irradiation with Helium Ions

Tynyshbayeva,

Kozlovskiy,

Rakhimov

et al. 2023

Materials

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The purpose of this work is to simulate the processes of gaseous swelling in SiC ceramics as well as the associated changes in strength and thermophysical properties under high-temperature irradiation with helium ions. The choices of irradiation conditions (irradiation temperatures of 700 and 1000 K) and irradiation fluences (1015–1018 ion/cm2) are based on the possibilities of modeling the processes of destructive changes in the near-surface layer as a result of the accumulation of gas-filled inclusions during high-dose irradiation. During this study, it was found that an increase in the irradiation temperature of the samples from 700 to 1000 K leads to a decrease in the resistance to gas swelling, since with the temperature increase, the mobility of implanted helium in the near-surface layer grows, which results in an increase in the size of gas-filled bubbles and, as a result, accelerated destruction of the damaged layer. It has been established that in the case of irradiation at 700 K, the critical fluence for swelling associated with the formation of visible gas-filled bubbles on the surface is 5 × 1017 ion/cm2, while for samples irradiated at a temperature of 1000 K, the formation of gas-filled bubbles is observed at a fluence of 1017 ion/cm2. Measurements of the thermal conductivity coefficient showed that the formation of gas-filled bubbles leads to a sharp deterioration in heat transfer processes, which indicates that the created defective inclusions prevent phonon heat transfer. Changes in the strength characteristics showed that a decrease in hardness occurs throughout the entire depth of the damaged ceramic layer. However, with a rise in the irradiation fluence above 1017 ion/cm2, a slight damaged layer thickness growth associated with diffusion processes of helium implantation into the near-surface layer is observed. The relevance of this study consists in obtaining new data on the stability of the strength and thermophysical parameters of SiC ceramics in the case of helium accumulation and its subsequent radiation-induced evolution in the case of irradiation at temperatures of 700 and 1000 K. The data obtained during the experimental work on changes in the properties of ceramics will make it possible to determine the potential limits of their applicability in the case of operation under extreme conditions at elevated temperatures in the future.

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A quantitative method to determine the region not influenced by injected interstitial and surface effects during void swelling in ion-irradiated metals

Cited by 13 publications

References 66 publications

Effect of Carbon on Void Nucleation in Iron

Effect of Carbon on Void Nucleation in Iron

Features of Helium–Vacancy Complex Formation at the Zr/Nb Interface

Study of The Gas-Swelling Mechanisms in Silicon Carbide Ceramics under High-Temperature Irradiation with Helium Ions

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