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Bilyk T, Goryaeva AM, Marinica MC, Flament C, Sabathier C, Leroy E, Loyer-Prost M, Meslin E. Accurate quantification of dislocation loops in complex functional alloys enabled by deep learning image analysis. Sci Rep 2024; 14:25168. [PMID: 39448616 PMCID: PMC11502901 DOI: 10.1038/s41598-024-74894-4] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Grants] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 04/05/2024] [Accepted: 09/30/2024] [Indexed: 10/26/2024] Open
Abstract
In-depth statistics of individual defects observed during transmission electron microscopy (TEM) experiments are essential for the thorough characterization of materials. In this study, we aim to quantitatively characterize the population of dislocation loops in ion-irradiated CrFeMnNi alloys. To this end, we propose an efficient guideline to prepare TEM micrographs dataset for deep learning analysis, adapted for accurate characterization of microstructures produced by thousands of overlapping defects, a very common situation in TEM images, unfeasible by previous existing methods. To reduce human effort, we annotate only a few images and complement the database through a two-step process: initially, singular value decomposition to normalize image background, followed by a controlled data augmentation. The performed analysis provides precise quantitative information about the number of loops of different types, as well as their spatial distribution, their size, and the inter-object distances. These characteristics provide insights into the nucleation, mobility, and growth of dislocation loops, as well as the elastic anisotropy of the material. Our results emphasize how accurate analysis of complex microstructures can provide insights into the physical properties of materials and open up many perspectives for attaining quantitative information on materials properties based solely on their image analysis.
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Affiliation(s)
- Thomas Bilyk
- Université Paris-Saclay, CEA, Service de recherche en Corrosion et Comportement des Matériaux, SRMP, 91191, Gif-sur-Yvette, France
| | - Alexandra M Goryaeva
- Université Paris-Saclay, CEA, Service de recherche en Corrosion et Comportement des Matériaux, SRMP, 91191, Gif-sur-Yvette, France
| | - Mihai-Cosmin Marinica
- Université Paris-Saclay, CEA, Service de recherche en Corrosion et Comportement des Matériaux, SRMP, 91191, Gif-sur-Yvette, France
| | - Camille Flament
- Université Grenoble Alpes, CEA, LITEN, 38000, Grenoble, France
| | | | - Eric Leroy
- Université Paris-Est Créteil, CNRS, ICMPE, UMR 7182, 94320, Thiais, France
| | - Marie Loyer-Prost
- Université Paris-Saclay, CEA, Service de recherche en Corrosion et Comportement des Matériaux, SRMP, 91191, Gif-sur-Yvette, France
| | - Estelle Meslin
- Université Paris-Saclay, CEA, Service de recherche en Corrosion et Comportement des Matériaux, SRMP, 91191, Gif-sur-Yvette, France.
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Yang G, Bao Y, Chen X, Ji C, Wei B, Liu W, Wang X. A simulation study of irradiation effect on InAs/GaAsSb type II quantum dot structures. Heliyon 2024; 10:e33910. [PMID: 39050463 PMCID: PMC11268345 DOI: 10.1016/j.heliyon.2024.e33910] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 02/22/2024] [Revised: 06/14/2024] [Accepted: 06/28/2024] [Indexed: 07/27/2024] Open
Abstract
Particles in space cause irradiation damage to the solar cells (SCs), resulting in the degradation of their performance. Quantum dot solar cells (QDSCs) have higher theoretical efficiency and better irradiation resistance than the conventional GaAs SCs, which makes them highly promising for application in space. In this paper, we study the proton irradiation effect on InAs/GaAs0.8Sb0.2 QDSCs by SRIM program. The simulation result shows that the InAs/GaAs0.8Sb0.2 QDSCs have fewer vacancies than GaAs SCs when irradiated with low-energy proton, which indicates that the InAs/GaAs0.8Sb0.2 QDSCs have better anti-irradiation characteristics. The study about displacements per atom and proton concentration in two SCs shows that protons with low energy and high irradiation fluences will cause more serious damage in InAs/GaAs0.8Sb0.2 QDSCs. In addition, the proton incident angle affects the vacancy distribution, while the number of QD layers has little effect on it.
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Affiliation(s)
- Guiqiang Yang
- Engineering Research Center for Semiconductor Integrated Technology, Institute of Semiconductors, Chinese Academy of Sciences, Beijing, 100083, China
- Center of Materials Science and Optoelectronics Engineering & School of Integrated Circuits, University of Chinese Academy of Sciences, Beijing, 100049, China
| | - Yidi Bao
- Engineering Research Center for Semiconductor Integrated Technology, Institute of Semiconductors, Chinese Academy of Sciences, Beijing, 100083, China
- Center of Materials Science and Optoelectronics Engineering & School of Integrated Circuits, University of Chinese Academy of Sciences, Beijing, 100049, China
| | - Xiaoling Chen
- Engineering Research Center for Semiconductor Integrated Technology, Institute of Semiconductors, Chinese Academy of Sciences, Beijing, 100083, China
- Center of Materials Science and Optoelectronics Engineering & School of Integrated Circuits, University of Chinese Academy of Sciences, Beijing, 100049, China
| | - Chunxue Ji
- Engineering Research Center for Semiconductor Integrated Technology, Institute of Semiconductors, Chinese Academy of Sciences, Beijing, 100083, China
- Center of Materials Science and Optoelectronics Engineering & School of Integrated Circuits, University of Chinese Academy of Sciences, Beijing, 100049, China
| | - Bo Wei
- Engineering Research Center for Semiconductor Integrated Technology, Institute of Semiconductors, Chinese Academy of Sciences, Beijing, 100083, China
- Center of Materials Science and Optoelectronics Engineering & School of Integrated Circuits, University of Chinese Academy of Sciences, Beijing, 100049, China
| | - Wen Liu
- Engineering Research Center for Semiconductor Integrated Technology, Institute of Semiconductors, Chinese Academy of Sciences, Beijing, 100083, China
- Center of Materials Science and Optoelectronics Engineering & School of Integrated Circuits, University of Chinese Academy of Sciences, Beijing, 100049, China
- Beijing Engineering Research Center of Semiconductor Micro-Nano Integrated Technology, Beijing, 100083, China
| | - Xiaodong Wang
- Engineering Research Center for Semiconductor Integrated Technology, Institute of Semiconductors, Chinese Academy of Sciences, Beijing, 100083, China
- Center of Materials Science and Optoelectronics Engineering & School of Integrated Circuits, University of Chinese Academy of Sciences, Beijing, 100049, China
- Beijing Engineering Research Center of Semiconductor Micro-Nano Integrated Technology, Beijing, 100083, China
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Wyszkowska E, Mieszczynski C, Kurpaska Ł, Azarov A, Jóźwik I, Kosińska A, Chromiński W, Diduszko R, Huo WY, Cieślik I, Jagielski J. Tuning heterogeneous ion-radiation damage by composition in Ni xFe 1-x binary single crystals. NANOSCALE 2023; 15:4870-4881. [PMID: 36779233 DOI: 10.1039/d2nr06178c] [Citation(s) in RCA: 1] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 06/18/2023]
Abstract
Radiation-induced heterogeneous damage is the single largest source of failures seen in structural components in nuclear power reactors. Single crystal materials without grain boundaries, show considerable promise for overcoming this problem. In this work, such heterogeneous damage was further overcome in NixFe1-x single crystal alloys via a simple strategy of fine-tuning the composition. [001] NixFe1-x (x = 0, 0.38 and 0.62 at%) single crystals prepared using the Bridgman method were irradiated over a wide fluence range (4 × 1013 to 4 × 1015 ions per cm2). The irradiation-induced defect evolution was studied using Rutherford backscattering/channeling spectrometry, Monte Carlo simulations, transmission electron microscopy and nanoindentation. The results indicate an increased radiation tolerance of Ni0.38Fe0.62 compared to pure Ni and Ni0.62Fe0.38. The structural analysis performed by transmission electron microscopy revealed that defects tend to agglomerate at one place in Ni and Ni0.62Fe0.38, while in Ni0.38Fe0.62 no defect accumulation zone (characteristic damage peak) has been captured either at low or high fluence. Moreover, we found that the hardness change with the increase of Fe content is due to different arrangements of Fe atoms in the crystal structure, which influences the obtained mechanical properties of NixFe1-x in the pristine state and after ion implantation.
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Affiliation(s)
- E Wyszkowska
- National Centre for Nuclear Research, NOMATEN CoE MAB+, Andrzeja Soltana 7, 05-400 Otwock-Swierk, Poland.
| | - C Mieszczynski
- National Centre for Nuclear Research, NOMATEN CoE MAB+, Andrzeja Soltana 7, 05-400 Otwock-Swierk, Poland.
| | - Ł Kurpaska
- National Centre for Nuclear Research, NOMATEN CoE MAB+, Andrzeja Soltana 7, 05-400 Otwock-Swierk, Poland.
| | - A Azarov
- Centre for Materials Science and Nanotechnology, University of Oslo, PO Box 1048 Blindern, N-0316 Oslo, Norway
| | - I Jóźwik
- National Centre for Nuclear Research, NOMATEN CoE MAB+, Andrzeja Soltana 7, 05-400 Otwock-Swierk, Poland.
| | - A Kosińska
- National Centre for Nuclear Research, NOMATEN CoE MAB+, Andrzeja Soltana 7, 05-400 Otwock-Swierk, Poland.
| | - W Chromiński
- National Centre for Nuclear Research, NOMATEN CoE MAB+, Andrzeja Soltana 7, 05-400 Otwock-Swierk, Poland.
- Warsaw University of Technology, Faculty of Materials Science and Engineering, Wołoska 141, 02-507 Warsaw, Poland
| | - R Diduszko
- National Centre for Nuclear Research, NOMATEN CoE MAB+, Andrzeja Soltana 7, 05-400 Otwock-Swierk, Poland.
- Lukasiewicz Research Network - Institute of Microelectronics and Photonics, Al. Lotników 32/46, Warsaw, Poland
| | - W Y Huo
- National Centre for Nuclear Research, NOMATEN CoE MAB+, Andrzeja Soltana 7, 05-400 Otwock-Swierk, Poland.
| | - I Cieślik
- National Centre for Nuclear Research, NOMATEN CoE MAB+, Andrzeja Soltana 7, 05-400 Otwock-Swierk, Poland.
| | - J Jagielski
- National Centre for Nuclear Research, NOMATEN CoE MAB+, Andrzeja Soltana 7, 05-400 Otwock-Swierk, Poland.
- Lukasiewicz Research Network - Institute of Microelectronics and Photonics, Al. Lotników 32/46, Warsaw, Poland
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Chen S. New evaluation of neutron-induced displacement damage cross section for EUROFER97. NUCLEAR MATERIALS AND ENERGY 2022. [DOI: 10.1016/j.nme.2022.101284] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/09/2022]
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Radiation-Induced Sharpening in Cr-Coated Zirconium Alloy. MATERIALS 2022; 15:ma15062322. [PMID: 35329774 PMCID: PMC8951102 DOI: 10.3390/ma15062322] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Download PDF] [Figures] [Subscribe] [Scholar Register] [Received: 03/03/2022] [Revised: 03/15/2022] [Accepted: 03/17/2022] [Indexed: 11/16/2022]
Abstract
To improve the safety of nuclear power plants, a Cr protective layer is deposited on zirconium alloys to enhance oxidation resistance of the nuclear fuel cladding during both in-service and hypothetical accidental transients at High Temperature (HT) in Light Water Reactors. The formation of the Cr2O3 film on the coating surface considerably helps in reducing the oxidation kinetics of the zirconium alloy, especially during hypothetic Loss of Coolant Accident (LOCA). However, if the Cr coating is successful to increase the oxidation resistance at HT of the zirconium substrate, for in-service conditions, under neutron irradiation, Cr desquamation has to be avoided to guarantee a safe use of the Cr-coated zirconium alloys. Therefore, the adhesion properties have to be maintained despite the structural defects created by sustained neutron irradiation in the reactor environment. This paper proposes to study the behavior of the Zircaloy-Cr interface of a first generation Cr-coated material during a specific in situ ion irradiation. As deposited, the Cr-coated sample presents a f.c.c. C15 Laves-type intermetallic phase at the interface with off-stoichiometric composition. After irradiation and for the specific conditions applied, this interfacial phase has significantly dissolved. Energy Dispersion Spectroscopy revealed that the dissolution was accompanied by a counterintuitive "sharpening" effect.
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Gupta R, Kumar V, Ram J, Chauhan V, Gupta D, Kumar S, Koratkar N, Kumar R. Influence of high energy (MeV) Au9+ ion irradiation for modification of properties in scaffold-assisted electro synthesized PbSe nanowires. INORG CHEM COMMUN 2022. [DOI: 10.1016/j.inoche.2021.109093] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/05/2022]
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Tuning surface wettability of molybdenum oxide nanorod mesh by low energy ion beam irradiation. Radiat Phys Chem Oxf Engl 1993 2021. [DOI: 10.1016/j.radphyschem.2021.109649] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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Nano-Structured Materials under Irradiation: Oxide Dispersion-Strengthened Steels. NANOMATERIALS 2021; 11:nano11102590. [PMID: 34685031 PMCID: PMC8538775 DOI: 10.3390/nano11102590] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Download PDF] [Figures] [Subscribe] [Scholar Register] [Received: 07/28/2021] [Revised: 09/27/2021] [Accepted: 09/28/2021] [Indexed: 11/30/2022]
Abstract
Oxide dispersion-strengthened materials are reinforced by a (Y, Ti, O) nano-oxide dispersion and thus can be considered as nanostructured materials. In this alloy, most of the nanoprecipitates are (Y, Ti, O) nano-oxides exhibiting a Y2Ti2O7 pyrochlore-like structure. However, the lattice structure of the smallest oxides is difficult to determine, but it is likely to be close to the atomic structure of the host matrix. Designed to serve in extreme environments—i.e., a nuclear power plant—the challenge for ODS steels is to preserve the nano-oxide dispersion under irradiation in order to maintain the excellent creep properties of the alloy in the reactor. Under irradiation, the nano-oxides exhibit different behaviour as a function of the temperature. At low temperature, the nano-oxides tend to dissolve owing to the frequent ballistic ejection of the solute atoms. At medium temperature, the thermal diffusion balances the ballistic dissolution, and the nano-oxides display an apparent stability. At high temperature, the nano-oxides start to coarsen, resulting in an increase in their size and a decrease in their number density. If the small nano-oxides coarsen through a radiation-enhanced Ostwald ripening mechanism, some large oxides disappear to the benefit of the small ones through a radiation-induced inverse Ostwald ripening. In conclusion, it is suggested that, under irradiation, the nano-oxide dispersion prevails over dislocations, grain boundaries and free surfaces to remove the point defects created by irradiation.
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