Au and Ag ion irradiation effects on the carbide precipitation and Ar bubble formation in solubilized AISI 316L alloys

Timm, Mariana de Mello; Oyarzabal, Ítalo M.; Tatsch, Francine; Amaral, L.; Fichtner, P.F.P.

doi:10.1016/j.nimb.2018.12.031

Cited by 9 publications

(5 citation statements)

References 10 publications

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“…[ 50 ] Although such retardation has been similarly reported in age‐hardenable Fe‐C alloys, [ 59,60 ] this phenomenon is opposed to common reports on austenitic stainless steels under energetic irradiation environments. [ 61–64 ] Recent values of solute‐vacancy binding energies were calculated by Wolverton; [ 65 ] ii)Guinier‐Preston zones (GPZs) and precipitation kinetics acceleration: as a result of neutron‐induced activation and transmutation of 27 AI, 28 Si via the nuclear reaction shown in Equation (), [ 66 ] increased nucleation and growth rates of GPZs and precipitation of phases such as Mg

_{2}

Si were observed in commercial AlMg and AlMgSi alloys at temperatures where vacancies are mobile. [ 50,53 ] Acceleration of

θ^{'}

‐phase (Al

_{2}

Cu) precipitation in Al‐based Cu containing alloys was also reported under low temperature neutron irradiation.…”

Section: Introductionmentioning

confidence: 99%

Prototypic Lightweight Alloy Design for Stellar‐Radiation Environments

et al. 2020

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The existing literature data shows that conventional aluminium alloys may not be suitable for use in stellar-radiation environments as their hardening phases are prone to dissolve upon exposure to energetic irradiation, resulting in alloy softening which may reduce the lifetime of such materials impairing future human-based space missions. The innovative methodology of crossover alloying is herein used to synthesize an aluminium alloy with a radiation resistant hardening phase. This alloy-a crossover of 5xxx and 7xxx series Al-alloys-is subjected to extreme heavy ion irradiations in situ within a TEM up to a dose of 1 dpa and major experimental observations are made: the Mg 32 (Zn,Al) 49 hardening precipitates (denoted as T-phase) for this alloy system surprisingly survive the extreme irradiation conditions, no cavities are found to nucleate and displacement damage is observed to develop in the form of black-spots. This discovery indicates that a high phase fraction of hardening precipitates is a crucial parameter for achieving superior radiation tolerance. Based on such observations, this current work sets new guidelines for the design of metallic alloys for space exploration.

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_{2}

Si were observed in commercial AlMg and AlMgSi alloys at temperatures where vacancies are mobile. [ 50,53 ] Acceleration of

θ^{'}

‐phase (Al

_{2}

Cu) precipitation in Al‐based Cu containing alloys was also reported under low temperature neutron irradiation.…”

Section: Introductionmentioning

confidence: 99%

Prototypic Lightweight Alloy Design for Stellar‐Radiation Environments

et al. 2020

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“…Tunes et al [ 44 ] recently reported 30 keV Xe-irradiated an austenitic stainless steel at 800 °C and argued that inert gas bubbles can accelerate clustering and precipitation kinetics. Similarly, vacancy-type defects can enhance the nucleation of carbide precipitations in Ar-irradiated AISI 316L alloys [ 45 ]. Fang et al [ 46 ] investigated Fe-irradiated SIMP steel at 300 °C and 400 °C and regarded the Si element enrichment and Ta element depletion inside the precipitates after 1 dpa irradiation at 300 °C.…”

Section: Resultsmentioning

confidence: 99%

Comparison between Subsequent Irradiation and Co-Irradiation into SIMP Steel

et al. 2021

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A modern Chinese ferritic/martensitic steel SIMP, is a new perspective nuclear structural material for the spallation target in accelerator driven sub-critical system. In this work, aimed at exploring the radiation resistance properties of this material, we investigate the differences between simultaneous Fe and He ions irradiation and He implantation of SIMP steel pre-irradiated by Fe self-ions. The irradiations were performed at 300 °C. The radiation-induced hardening was evaluated by nano-indentation, while the lattice disorder was investigated by transmission electron microscopy. Clear differences were found in the material microstructure after the two kinds of the ion irradiation performed. Helium cavities were observed in the co-irradiated SIMP steel, but not the case of He implantation with Fe pre-irradiation. In the same time, the size and density of Frank loops were different in the two different irradiation conditions. The reason for the different observed lattice disorders is discussed.

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“…They have also been considered as structural components in innovative nuclear fusion test reactors due to the very good results they have obtained in applications in extreme environments [ 117 , 118 , 119 ]. The 300 series steels (Fe-Cr-Ni alloy) have good corrosion and mechanical properties for applications at high temperatures, making them viable to be applied in aeroengine parts, turbochargers, oil and gas pipelines [ 115 , 116 , 117 , 118 , 119 , 120 , 121 , 122 , 123 , 124 , 125 , 126 , 127 , 128 , 129 , 130 , 131 ], and as structural components in nuclear reactors [ 116 , 117 , 132 , 133 ]. The 304 SS is one of the austenitic steels that is most used in nuclear reactors.…”

Section: Relations Between Microstructures and Alloys Performance Of ...mentioning

confidence: 99%

Aspects of Applied Chemistry Related to Future Goals of Safety and Efficiency in Materials Development for Nuclear Energy

Golgovici

Tudose²,

Diniasi³

et al. 2023

Molecules

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The present paper is a narrative review focused on a few important aspects and moments of trends surrounding materials and methods in sustainable nuclear energy, as an expression of applied chemistry support for more efficiency and safety. In such context, the paper is focused firstly on increasing alloy performance by modifying compositions, and elaborating and testing novel coatings on Zr alloys and stainless steel. For future generation reactor systems, the paper proposes high entropy alloys presenting their composition selection and irradiation damage. Nowadays, when great uncertainties and complex social, environmental, and political factors influence energy type selection, any challenge in this field is based on the concept of increased security and materials performance leading to more investigations into applied science.

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Au and Ag ion irradiation effects on the carbide precipitation and Ar bubble formation in solubilized AISI 316L alloys

Cited by 9 publications

References 10 publications

Prototypic Lightweight Alloy Design for Stellar‐Radiation Environments

Prototypic Lightweight Alloy Design for Stellar‐Radiation Environments

Comparison between Subsequent Irradiation and Co-Irradiation into SIMP Steel

Aspects of Applied Chemistry Related to Future Goals of Safety and Efficiency in Materials Development for Nuclear Energy

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