Article
Materials Science, Multidisciplinary
Rakesh Kumar Barik, Sankalp Biswal, Amlan Dutta, Debalay Chakrabarti, Abhijit Ghosh
Summary: Screw dislocation motion in bcc Fe has a significant impact on the temperature and strain rate sensitivity of flow stress, leading to the transition from ductile to brittle behavior in steel. Addition of solute atoms with attractive interaction with screw dislocations can reduce the flow stress sensitivity of Fe. This study investigates the effect of Ni and Cu solute atom distribution on screw dislocation motion in bcc Fe through molecular statics and dynamics simulations. Results show that the local distribution of Ni atoms greatly influences the Peierls stress of Fe, while Cu atom distribution has minimal effect. Furthermore, the presence of Ni/Cu atoms ahead of the dislocation line helps reduce the Peierls stress due to the attractive interaction with dislocations.
COMPUTATIONAL MATERIALS SCIENCE
(2023)
Article
Chemistry, Physical
Tiantian Shi, Wenbo Liu, Zhengxiong Su, Xu Yan, Chenyang Lu, Di Yun
Summary: In this study, the microstructural evolution of Fe-Cr alloys under irradiation was investigated by TEM. Results showed that the size of dislocation loops in Fe-9Cr-C alloy was larger but with lower density compared to Fe-9Cr alloy. Irradiation at 550 degrees C resulted in the rapid conversion of dislocation loops into network dislocations. Subgrains were also observed in the alloys after irradiation.
Article
Materials Science, Multidisciplinary
Zhen-Ming Hua, Min Zha, Zhao-Yuan Meng, Shen-Bao Jin, Gang Sha, Tian-Shuai Wang, Cheng Wang, Hai-Long Jia, Yipeng Gao, Hui-Yuan Wang
Summary: By manipulating solute distribution while keeping a fine-grain structure, achieving appreciable strain-aging hardening response coupling with fine-grain strengthening guarantees the development of strong dilute Mg alloy.
MATERIALS RESEARCH LETTERS
(2022)
Article
Materials Science, Multidisciplinary
Krishna Chaitanya Pitike, Wahyu Setyawan
Summary: Nanostructured Ferritic Alloys (NFAs) containing oxide nanoparticles are potential advanced structural materials for fusion reactors. Due to the lack of fusion neutron sources with sufficient flux, modeling is crucial for understanding radiation damage and helium effects in NFAs. Machine learning interatomic potentials (MLPs) are chosen to study helium bubble accumulation in NFAs.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Chemistry, Multidisciplinary
Samik Mukherjee, Simone Assali, Oussama Moutanabbir
Summary: This study using GeSn semiconductor as a model system reveals the atomic-level details of solute behavior near a dislocation before surface segregation in strained, metastable thin layers. The migration of solute atoms towards dislocations during the initial phase separation leads to an increase in Sn concentration and density of atomic clusters.
Article
Physics, Condensed Matter
P. S. V. R. A. Kishor, Prince Gollapalli, Debolina Misra, Prajeet Oza, Satyesh Kumar Yadav
Summary: This study examines the preference of solute atoms for different sites in Fe using first-principles density functional theory. The results show that the preference of O for the octahedral site is determined by the electronic binding energy (EBE), while the distortion energy (DE) is highest at that site. The preference of C and N in bulk Fe is influenced by both DE and EBE. However, DE alone dictates the site preference for B. The DE of solute atoms cannot be predicted by their calculated radius, as B, despite having the largest radius, has similar distortion energy to O due to a large charge transfer.
PHYSICA B-CONDENSED MATTER
(2023)
Article
Nanoscience & Nanotechnology
Yu Wen, Bo Guan, Yunchang Xin, Chenglu Liu, Peidong Wu, Guangjie Huang, Qing Liu
Summary: The solute atom mediated Hall-Petch relations were investigated for Mg-Y, Mg-Al, Mg-Gd, and Mg-Zn alloys at a nominal solute content of 0.35 at.%. It was found that Mg-Y and Mg-Gd exhibited significantly lower Hall-Petch slope (k) values (220 MPa·μm(1/2) and 285 MPa·μm(1/2), respectively) compared to Mg-Al and Mg-Zn (324 MPa·μm(1/2) and 322 MPa·μm(1/2), respectively) under compression along the extrusion direction. The addition of Zn or Al led to a strong basal texture and predominantly basal slip deformation, while the addition of Gd or Y resulted in a weakened texture and activation of both {10 (1) over bar2} twinning and basal slip. This difference in deformation mechanisms contributed to the lower k values in Mg-Y and Mg-Gd alloys.
SCRIPTA MATERIALIA
(2022)
Article
Materials Science, Multidisciplinary
C. Dai, P. Saidi, B. Langelier, Q. Wang, C. D. Judge, M. R. Daymond, M. Mattucci
Summary: Radiation-induced segregation of alloying elements to crystallographic defects is commonly observed in irradiated austenitic stainless steels. The interaction between solutes and defects affects the physical distribution of solutes, which in turn affects the formation, growth, and mechanical properties of defects. Atom probe tomography and molecular dynamics simulations were used in this study to investigate the distribution of solutes and stress fields at dislocation loops in 304L stainless steel. The results show that at higher temperatures, enrichment and depletion of certain alloying elements occur at dislocation loops, while no segregation is observed at lower temperatures. The simulations reveal the formation of Cr clusters and the enrichment or depletion of Ni atoms at different types of dislocation loops.
PHYSICAL REVIEW MATERIALS
(2022)
Article
Materials Science, Multidisciplinary
S. Rao, C. Woodward, B. Akdim
Summary: In this study, solute-dislocation interaction energies are calculated using Density Functional Theory (DFT) and the 2-D lattice Greens function approach. These predictions are then used in an extension of the Rao-Suzuki model to analyze solid solution strengthening and softening in various crystals. The refined model shows good agreement with experimental observations and can be used in designing high strength, multi-component BCC alloys for high temperature applications.
Article
Chemistry, Physical
Yibo Wang, Songyuan Li, Feida Chen, Kun Yang, Guojia Ge, Xiaobin Tang, Minyu Fan, Ping Huang
Summary: In this research, EHEAs AlCrFeNiTix with different titanium contents were irradiated, and it was found that phase boundaries effectively decreased the density and size of dislocation loops, while the addition of titanium resulted in small-sized and high-density dislocation loops. Density function theory (DFT) results showed that the B2 phase was more suitable for accommodating titanium, and the lattice distortion effect caused by titanium in the B2 phase was more obvious than in the A2 phase. This study provides a beneficial scheme for solid solution strengthening of elements in EHEAs and offers insights into the suppression of dislocation loops under irradiation.
JOURNAL OF ALLOYS AND COMPOUNDS
(2023)
Article
Materials Science, Multidisciplinary
Yan-Ru Lin, Wei-Ying Chen, Meimei Li, Jean Henry, Steven John Zinkle
Summary: This study investigated the microstructural evolution of Fe and Fe-10Cr under irradiation conditions, revealing the mechanisms of different types of dislocation loops and the inhibitory effect of Cr and He addition on dislocation loop motion. With increasing irradiation dose, 1/2 <111> loops became the dominant type of loops.
Article
Materials Science, Multidisciplinary
Lan Li, Meng Sun, Ke Jing, Yunxia Gao, Weibin Jiang, Hui Wang, Qianfeng Fang, Xianping Wang
Summary: This study investigates the enhancing effect of Al addition and mechanical treatment on the room temperature ductility of Fe-Ga alloys. The results show that increasing the Al content significantly improves the ductility and eliminates discontinuous yielding behavior, while maintaining high damping capacities. The enhanced ductility is believed to be attributed to the interaction between dislocations and the secondary phase. The damping capacity gradually decreases with increasing Al content, which is suggested to be caused by the limitation of domain wall motion due to the additional domains.
JOURNAL OF MATERIALS RESEARCH AND TECHNOLOGY-JMR&T
(2022)
Article
Nuclear Science & Technology
K. Vogel, P. Chekhonin, C. Kaden, M. Hernandez-Mayoral, S. Akhmadaliev, F. Bergner
Summary: It is commonly believed that the microstructure of ion-irradiated Fe-based alloys is depth-dependent, with the arrangement of dislocation loops varying based on the profiles of displacement damage and injected interstitials. Differences in number densities and mean sizes of loops were observed between distinct depth ranges, with higher ion energy resulting in a wider range of loop decoration. The understanding of these depth dependencies is crucial for interpreting material behavior under irradiation and for optimizing characterization techniques like nanoindentation.
NUCLEAR MATERIALS AND ENERGY
(2021)
Article
Materials Science, Multidisciplinary
Markus Sudmanns, Jaafar A. El-Awady
Summary: This study introduces a formulation for considering the interaction between dislocations and substitutional solute atoms in fcc alloys in 3D DDD simulations. The model can explain phenomena such as slow dislocation motion, frequent cross-slip, and alignment with solute aggregation features observed in multi-principal element alloys.
Article
Chemistry, Physical
Yan-Kun Dou, Han Cao, Xin-Fu He, Jin Gao, Jin-li Cao, Wen Yang
Summary: The interactions between a 1/2 <110> {111} edge dislocation and a void in Fe10Ni20Cr and Fe33Ni33Cr concentrated solid-solution alloys were studied using molecular dynamics simulation. It was found that the dislocation motion becomes more difficult in Fe33Ni33Cr alloy due to larger fluctuations in stacking fault energy compared to Fe10Ni20Cr alloy. However, Fe33Ni33Cr alloy exhibits better irradiation hardening resistance than Fe10Ni20Cr alloy, especially at high temperatures.
JOURNAL OF ALLOYS AND COMPOUNDS
(2021)
Article
Physics, Fluids & Plasmas
A. De Backer, D. R. Mason, C. Domain, D. Nguyen-Manh, M. -C. Marinica, L. Ventelon, C. S. Becquart, S. L. Dudarev
Article
Materials Science, Multidisciplinary
N. Castin, M. I. Pascuet, L. Messina, C. Domain, P. Olsson, R. C. Pasianot, L. Malerba
COMPUTATIONAL MATERIALS SCIENCE
(2018)
Article
Materials Science, Multidisciplinary
C. S. Becquart, R. Ngayam Happy, P. Olsson, C. Domain
JOURNAL OF NUCLEAR MATERIALS
(2018)
Article
Physics, Condensed Matter
R. Candela, N. Mousseau, R. G. A. Veiga, C. Domain, C. S. Becquart
JOURNAL OF PHYSICS-CONDENSED MATTER
(2018)
Article
Nanoscience & Nanotechnology
Yan Zhao, Binyan He, Sebastien Saillet, Christophe Domain, Patrick Le Delliou, Michel Perez, Rongshan Qin
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
(2018)
Article
Materials Science, Multidisciplinary
R. Badyka, G. Monnet, S. Saillet, C. Domain, C. Pareige
JOURNAL OF NUCLEAR MATERIALS
(2019)
Article
Materials Science, Multidisciplinary
G. Bonny, C. Domain, N. Castin, P. Olsson, L. Malerba
COMPUTATIONAL MATERIALS SCIENCE
(2019)
Article
Materials Science, Multidisciplinary
Salim Ferhat, Christophe Domains, Julien Vidal, Didier Noel, Bernard Ratier, Bruno Lucas
ORGANIC ELECTRONICS
(2019)
Article
Materials Science, Multidisciplinary
Leifeng Zhang, Bertrand Radiguet, Patrick Todeschini, Christophe Domain, Yang Shen, Philippe Pareige
JOURNAL OF NUCLEAR MATERIALS
(2019)
Article
Materials Science, Multidisciplinary
B. Christiaen, C. Domain, L. Thuinet, A. Ambard, A. Legris
Article
Materials Science, Multidisciplinary
E. Toijer, L. Messina, C. Domain, J. Vidal, C. S. Becquart, P. Olsson
Summary: This study investigates radiation-induced segregation in face centered cubic Ni-X dilute binary alloys, examining the tendencies and effects of solutes during migration. The results show different segregation behaviors of solutes during radiation-induced migration, providing important insights into the kinetic properties of materials.
PHYSICAL REVIEW MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
M. J. Lloyd, A. J. London, J. C. Haley, M. R. Gilbert, C. S. Becquart, C. Domain, E. Martinez, M. P. Moody, P. A. J. Bagot, D. Nguyen-Manh, D. E. J. Armstrong
Summary: In this study, single crystal and polycrystalline tungsten samples irradiated at high temperature were characterized using Atom Probe Tomography and Scanning Transmission Electron Microscopy. The results showed the formation of Re and Os rich precipitates under neutron irradiation and observed new physical phenomena.
Article
Materials Science, Multidisciplinary
Alecsandre Sauve-Lacoursiere, Simon Gelin, Gilles Adjanor, Christophe Domain, Normand Mousseau
Summary: Traditionally, the diffusion rates of point defects are believed to be mainly influenced by energy barriers. However, in disordered environments, the entropic variations between local minima and activated states become increasingly important. The unexpectedly slower defect diffusion observed in high entropy alloys has prompted researchers to revisit the role of pre-factors.
Article
Multidisciplinary Sciences
Alexandra M. Goryaeva, Christophe Domain, Alain Chartier, Alexandre Dezaphie, Thomas D. Swinburne, Kan Ma, Marie Loyer-Prost, Jerome Creuze, Mihai-Cosmin Marinica
Summary: It has been commonly believed that defects in face-centred cubic metals form larger dislocation loops through the coalescence of interstitial dumbbells. However, this study reveals that interstitial atoms in these metals actually cluster into compact 3D inclusions of A15 Frank-Kasper phase before forming dislocation loops. These A15 nano-phase inclusions then act as a source for prismatic or faulted dislocation loops. This discovery provides a better understanding of the complex mechanisms behind interstitial defect formation in metals.
NATURE COMMUNICATIONS
(2023)
Article
Materials Science, Multidisciplinary
Liuming Wei, Jingwen Li, Yonggang Li, Qirong Zheng, Fan Cheng, Chuanguo Zhang, Jingyu Li, Gaofeng Zhao, Zhi Zeng
Summary: This study investigates the influence of He-V complexes on H behaviors on different W surfaces using DFT calculations. The results show that H dissolution is most difficult but H trapping is easiest on the W (110) surface, while the opposite is true on the W (111) surface. Moreover, the presence of He-V complexes increases the difficulty of H diffusion from bulk to surface and desorption.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Yan Meng, Song Zeng, Chen Chen, Chaowen Zhu, Huahai Shen, Xiaosong Zhou, Xiaochun Han
Summary: The characteristics of magnetron sputtered Cr coatings vary with different temperature, bias voltage, and pressure. Coatings with random orientation, good crystallinity, and small grain size exhibit favorable oxidation behavior, while coatings with strong (200) texture, poor crystallinity, and large grains have many intrinsic defects that are detrimental to the protection property of the Cr coatings.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Xinyuan Xu, Zefeng Yu, Wei-Ying Chen, Aiping Chen, Arthur Motta, Xing Wang
Summary: This study presents an automated approach for characterizing grain morphology in TEM images recorded during ion irradiation. By combining a machine learning model and a computer vision algorithm, comparable results to human analysis can be achieved with significantly reduced analysis time. Researchers can train their own models following the procedures described in this study to automate grain morphology analysis of their own TEM images.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Shihao Wu, Dong Wang, Yapei Zhang, Koji Okamoto, Marco Pellegrini, Wenxi Tian, Suizheng Qiu, G. H. Su
Summary: The oxidation and degradation mechanisms of Cr coating on Zr alloy cladding under high temperature steam atmosphere are summarized, and a mathematical analysis model is established to predict the changes in coating thickness. The model is applied in the analysis of structure evolution under different conditions.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
V. Diaz-Mena, J. de Prado, M. Roldan, I. Izaguirre, M. Sanchez, M. Rieth, A. Urena
Summary: The brazeability of a cupronickel alloy was evaluated as a filler alloy for high-temperature joining of tungsten to steel. The study investigated the brazing conditions and the impact of the selected filler on the joint quality using numerical software. The results showed different metallurgical interactions and diffusion phenomena between the filler alloy and the base materials at different temperatures. The study emphasized the importance of selecting a suitable filler to mitigate residual stresses in the joints.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Pengcheng Zhu, Yajie Zhao, Yan-Ru Lin, Jean Henry, Steven J. Zinkle
Summary: This study investigates the effect of heavy-ion irradiation on radiation hardening in high-purity binary alloy Fe18Cr. Nanoindentation testing and high-quality TEM imaging were conducted to extract hardness and microstructure information. The strength factor was accurately calculated based on the detailed TEM characterization of irradiated microstructures, and a refined hardening superposition method was applied to quantify the mechanical properties of ion-irradiated materials.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Bin Wu, Haixia Ning, Hanzhen Zhu, Jianjun Chen, Kang Wang, Daiyu Zhang, Fu Wang, Qilong Liao
Summary: This study discusses the effects of ZrO2 and B2O3 on the phase composition and properties of SAP-based glass-ceramics. The results show that ZrO2 addition improves the formation of NZP phase while restricting the crystallization of AlPO4 phases. The correct ratios of ZrO2 and B2O3 allow only the formation of NZP phase within the SAP glass.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Hwasung Yeom, Greg Johnson, Benjamin Maier, Tyler Dabney, Kumar Sridharan
Summary: Cr-Nb bilayer coatings were developed using cold spray deposition to improve the limiting operational temperature of Cr-coated Zr-alloy system. The coatings exhibited outstanding oxidation resistance at high temperatures and formed continuous intermetallic compound layers at the interfaces.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Padhraic L. Mulligan, Andrew T. Nelson, Chad M. Parish, Patrick A. Champlin, Xiang Chen, Daniel Morrall, Jason M. Harp
Summary: Environmental barrier coatings are being developed to reduce oxidation and embrittlement in Zr-based materials. Chromium nitride is a candidate for this application, but understanding its impact on irradiation-induced creep and microstructure is critical.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Dexuan Yan, Xinlei Cao, Ke Shen
Summary: This study investigated the purification mechanism of polycrystalline graphite by comparing IG-11 graphite with IG-110 nuclear grade graphite. The analysis revealed that metallic impurities in IG-11 were primarily segregated within graphite porosities, while IG-110 demonstrated a significant reduction in impurities. This research contributes to the development of innovative graphite purification techniques for greater purity and stronger oxidation resistance.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Wei Xu, Wei Peng, Lei Shi, Qi Sun
Summary: This paper investigates the oxidation and shape evolution of matrix graphite in high temperature gas-cooled reactors during air-ingress accidents. A reaction kinetics model is established and computational fluid dynamics with a dynamic mesh method is used to simulate the oxidation process. The results show that the geometric shape of graphite changes significantly with increasing flow rate, and the graphite pebbles tend to form a structure with a narrow front and wide tail.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Allison Harward, Casey Elliott, Michael Shaltry, Krista Carlson, Tae-Sic Yoo, Guy Fredrickson, Michael Patterson, Michael F. Simpson
Summary: This paper investigates the hygroscopic properties of eutectic LiCl-KCl absorbed into zeolite-4A. The study finds that water absorption and corrosion worsen with increasing salt loading. It also suggests that the salt can be stored in a non-inert atmosphere for a certain period of time.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Takaaki Koyanagi, Xunxiang Hu, Christian M. Petrie, Gyanender Singh, Caen Ang, Christian P. Deck, Weon-Ju Kim, Daejong Kim, James Braun, Yutai Katoh
Summary: This study provides critical experimental data on the effects of irradiation on the hermeticity of SiC composite cladding, finding that irradiation can cause a decrease in hermeticity and cracking, and coating the outer surface can mitigate the cracking issue.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
S. Krat, A. Prishvitsyn, Yu. Gasparyan
Summary: This study proposes a probabilistic and diffusion-based model to describe the co-deposition of multiple hydrogen isotopes with slowly grown metal layers. The model calculates the relative concentrations of different hydrogen isotopes in the co-deposited metal layers. It is found that if hydrogen isotopes have different detrapping energies, only the isotope with the highest detrapping energy shows a monotonic decrease in concentration with deposition temperature. Furthermore, the study evaluates the uncertainty of tritium concentration in the co-deposited layer based on the uncertainty in detrapping energy of tritium and deuterium, predicting a >10% tritium concentration uncertainty for a 0.01 eV difference.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Tijo Vazhappilly, Arup Kumar Pathak
Summary: This study investigates the effect of Ce atom substitution in UO2 on its thermophysical properties using density functional theory. The results show that the Ce substitution levels and the oxidation state of Ce/U atoms strongly influence the band structure and specific heat capacity of the UO2 lattice. These findings provide important insights into the fuel properties of UO2 under reactor conditions.
JOURNAL OF NUCLEAR MATERIALS
(2024)