Article
Chemistry, Multidisciplinary
Joel Ribis, Isabelle Mouton, Cedric Baumier, Aurelie Gentils, Marie Loyer-Prost, Laurence Luneville, David Simeone
Summary: Oxide dispersion-strengthened materials are reinforced by (Y, Ti, O) nano-oxide dispersion and exhibit different behaviors of nano-oxides at different temperatures. Maintaining the nano-oxide dispersion under irradiation is crucial for preserving the excellent creep properties of the alloy in a nuclear power plant.
Article
Materials Science, Multidisciplinary
Ratnakar Singh, Ujjwal Prakash, Deepak Kumar, Kinkar Laha
Summary: The microstructure, crystal structure, and size distribution of oxide particles in oxide dispersion strengthened steels were investigated. The addition of yttria significantly reduces the ductility of the steel. This limitation can be overcome by powder forging of ODS steel powders.
MATERIALS CHARACTERIZATION
(2022)
Article
Chemistry, Physical
M. Frelek-Kozak, L. Kurpaska, K. Mulewska, M. Zielinski, R. Diduszko, A. Kosinska, D. Kalita, W. Chrominski, M. Turek, K. Kaszyca, A. Zaborowska, J. Jagielski
Summary: In this study, the authors conducted ion irradiation experiments to verify the structural and mechanical properties of materials strengthened by three different types of refractory oxides. The results showed a strong correlation between the strengthening oxide and the materials' microstructural and mechanical behavior under radiation damage. At low fluences, the mechanical properties in the modified layer of all materials were similar, while at high fluences, significant differences between the materials were observed.
APPLIED SURFACE SCIENCE
(2023)
Article
Chemistry, Physical
Zhaoyun Lin, Gang Shao, Wen Liu, Yiguang Wang, Hailong Wang, Hailiang Wang, Bingbing Fan, Hongxia Lu, Hongliang Xu, Rui Zhang
Summary: The dynamic transformations and damage behavior of free-standing multi-wall carbon nanotubes, carbon nano-onions, and nanodiamonds are studied using in-situ transmission electron microscope measurements. Key factors including hybridization, inherent defects, and morphology are employed to explore the disordering or graphitization process. Structural evolutions are described precisely using fluence calculations, interplanar spacing measurements, and inverse fast Fourier transformations.
Article
Materials Science, Multidisciplinary
Xi Qiu, Hua Pang, Guang Ran, Yong Xin, Yipeng Li, Qing Han, Wenjie Li, Xiaoming Chai, Shixin Gao, Quan Li, Yuanming Li, Yongjun Jiao
Summary: In-situ TEM observation was conducted to study the loop evolution in Mo-5 wt.%Re alloy under 400 keV Fe+ irradiation at 700°C and 800°C. The initiation of loops was observed throughout the irradiation process. Changes in dislocation line behavior and loop habit plane were observed in-situ, and the merging of three loops was facilitated by an intermediate bridge. Three main mechanisms for loop disappearance were identified, including loop aggregation, absorption by strong defect sinks, and the influence of surrounding loops. The study also investigated the relationship between irradiation parameters and the formation and behavior of loops. The in-situ observation of microstructure evolution provides valuable insights into the irradiation damage behavior of Mo-Re alloy.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Materials Science, Multidisciplinary
Arunodaya Bhattacharya, Samara M. Levine, Steven J. Zinkle, Wei-Ying Chen, Peter Baldo, Chad M. Parish, Philip D. Edmondson
Summary: In-situ irradiations using 1 MeV Kr2+ ions were performed on extraction replica samples of two ferritic-martensitic (FM) steels. The M23C6 carbides showed sensitivity to radiation induced amorphization (RIA), while the MX carbonitrides exhibited high amorphization resistance. The critical amorphization dose of M23C6 carbides increased exponentially with irradiation temperature. Changes in the minor chemistry of M23C6 had little effect on the amorphization behavior. In-situ irradiations on extraction replica samples provide a novel pathway to explore radiation tolerance of nanoprecipitates in nuclear structural materials.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Materials Science, Multidisciplinary
C. J. Ulmer, W-Y. Chen, D. E. Wolfe, A. T. Motta
Summary: Irradiation grain growth of CeO2 was studied using in-situ ion irradiation with TEM. The CeO2 phase remained stable and its grains grew with irradiation at elevated temperatures, showing weak dependence on irradiation temperature between 400°C and 800°C. The grain growth kinetics were evaluated by a thermal spike model to calculate the activation energy for grain growth.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Tim Graening, Michael Rieth, Harald Leiste, Michael Duerrschnabel, Anton Moeslang
Summary: Austenitic oxide dispersion strengthened steels were developed using mechanical alloying with a novel 2-step process and vanadium addition for process optimization. Characterization of chemical compositions, particle sizes, hardness, etc., and successful dual-precipitate formation through transmission electron microscopy methods were achieved.
MATERIALS & DESIGN
(2022)
Article
Materials Science, Multidisciplinary
S. M. Levine, C. Pareige, Z. Jiao, P. D. Edmondson, G. S. Was, S. J. Zinkle, A. Bhattacharya
Summary: This study investigated the stability of different solute nanoclusters during radiation and found that they have distinct ballistic dissolution susceptibilities. The results also demonstrated the importance of solute concentration gradient in recovering from ballistic dissolution.
MATERIALS & DESIGN
(2022)
Article
Materials Science, Multidisciplinary
Sung Eun Kim
Summary: The irradiation-induced creep behavior of Al-Sc binary alloy system is measured in TEM using cantilever beam methods. Al+ ion irradiation is employed to induce the creep. The experiments show that the creep compliance increases as the laser heating power (temperature) increases and exceeds 100 MPa, indicating a low stress creep mechanism. The microstructural behavior is also studied, revealing a dominant thermal diffusion and a high density of dislocation loops at temperatures higher than 400 degrees C.
METALS AND MATERIALS INTERNATIONAL
(2023)
Article
Materials Science, Multidisciplinary
Nargisse Khiara, Fabien Onimus, Stephanie Jublot-Leclerc, Thomas Jourdan, Thomas Pardoen, Jean-Pierre Raskin, Yves Brechet
Summary: In-situ TEM straining experiments were conducted on pure copper to investigate the dislocation behavior under heavy ion irradiation and high applied stress levels. The unpinning of dislocations from irradiation defects followed by glide was observed, suggesting a cascade-related mechanism explaining radiation induced dislocation glide. This work provides new insights into irradiation creep deformation at high stress levels.
Article
Materials Science, Multidisciplinary
Xuan Zhang, Wei-Ying Chen, Alexander Caputo
Summary: The study found that Alloy 709 stainless steel samples with different processing histories exhibit varying microstructural changes under high temperature irradiation, with creep-deformed samples showing the smallest dislocation loop size and lowest loop density. The sink strength factors in each sample play a role in influencing these changes.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Ceramics
Shanshan Xu, Ce Zheng, Yichun Bi, Qingping Mao, Hailong Qin, Xiaoqiang Li
Summary: SiC/SiC composites are promising materials for nuclear systems, and SiC fibers play a critical role in the performance of these composites. This study investigated the microstructural evolution of Cansas-III SiC fibers under temperature effects using in-situ transmission electron microscopy. The results showed that at room temperature, the SiC fibers experienced heterogeneous amorphization and became completely amorphous at a certain dose. At temperatures above the critical temperature for crystalline-to-amorphous transition, the fibers underwent carbon packet disappearance and nano-grain growth. Possible mechanisms were discussed.
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
(2023)
Article
Materials Science, Multidisciplinary
Meng Li, Zhang-Zhi Shi
Summary: This study investigated the morphology of nano-scale ZnO corrosion products and their orientation relationship with Zn matrix using TEM. A small volumetric strain of 0.63% was determined to achieve a low energy interfacial structure between the two phases. The method for quickly finding low energy interface under TEM by satisfying multiple Delta g//g in reciprocal space was proposed.
MATERIALS CHARACTERIZATION
(2021)
Article
Chemistry, Physical
Libing Yao, Peichao Zou, Lin Su, Yi Wu, Yuchen Pan, Ruining Fu, Huihua Min, Li Zhong, Huolin L. Xin, Litao Sun, Feng Xu
Summary: The research explores the potential of layered NH4V4O10 material as an anode material for sodium-ion batteries, revealing a reversible cycling capacity and long-term cycling stability through studying its sodium storage reaction mechanism and structural evolution.
Article
Physics, Multidisciplinary
A. Zahague, L. Brahim, A. Legris, R. Besson, L. Rabahi, B. Djamel
CHINESE JOURNAL OF PHYSICS
(2019)
Article
Materials Science, Ceramics
Guillaume Victor, Yves Pipon, Nathalie Moncoffre, Nicolas Bererd, Claude Esnouf, Thierry Douillard, Aurelie Gentils
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
(2019)
Article
Materials Science, Multidisciplinary
Remy Besson, Jerome Dequeker, Ludovic Thuinet, Alexandre Legris
Article
Materials Science, Multidisciplinary
B. Christiaen, C. Domain, L. Thuinet, A. Ambard, A. Legris
Article
Chemistry, Multidisciplinary
Yuki Kobayashi, Muneyuki Naito, Koichi Sudoh, Aurelie Gentils, Cyril Bachelet, Jerome Bourcois
CRYSTAL GROWTH & DESIGN
(2019)
Article
Materials Science, Multidisciplinary
B. Christiaen, C. Domain, L. Thuinet, A. Ambard, A. Legris
Article
Materials Science, Multidisciplinary
Gabriel Franck Bouobda Moladje, Ludovic Thuinet, Christophe Domain, Charlotte S. Becquart, Alexandre Legris
COMPUTATIONAL MATERIALS SCIENCE
(2020)
Article
Materials Science, Multidisciplinary
O. Emelyanova, A. Gentils, V. A. Borodin, M. G. Ganchenkova, P. V. Vladimirov, P. S. Dzhumaev, I. A. Golovchanskiy, R. Lindau, A. Moeslang
Summary: The study showed that different injection modes in ODS-EUROFER steel have varying effects on bubble formation and radiation stability, with nanoparticles potentially leading to a bubble-to-void transition. Quantitative assessment of bubble families can help prevent swelling acceleration.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Kai Duemmler, Ce Zheng, Cedric Baumier, Aurelie Gentils, Djamel Kaoumi
Summary: The formation of helium bubbles in Ferritic/Martensitic steel HT9 was investigated through in situ Transmission Electron Microscopy combined with helium implantation and heavy ion irradiation. The study focused on the effect of increasing helium appm/dpa ratio on the formation and growth of the bubbles, as well as the sequential order of ion irradiation.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Chemistry, Multidisciplinary
Joel Ribis, Isabelle Mouton, Cedric Baumier, Aurelie Gentils, Marie Loyer-Prost, Laurence Luneville, David Simeone
Summary: Oxide dispersion-strengthened materials are reinforced by (Y, Ti, O) nano-oxide dispersion and exhibit different behaviors of nano-oxides at different temperatures. Maintaining the nano-oxide dispersion under irradiation is crucial for preserving the excellent creep properties of the alloy in a nuclear power plant.
Article
Chemistry, Physical
Joel Ribis, Alexia Wu, Raphaelle Guillou, Jean-Christophe Brachet, Cedric Baumier, Aurelie Gentils, Marie Loyer-Prost
Summary: To improve the safety of nuclear power plants, a Cr protective layer is deposited on zirconium alloys to enhance oxidation resistance. However, the risk of Cr desquamation needs to be avoided for safe use of the Cr-coated zirconium alloys.
Article
Chemistry, Physical
Stephanie Jublot-Leclerc, Martin Owusu-Mensah, Vladimir A. Borodin, Joel Ribis, Ludovic Largeau, Ryan Schoell, Djamel Kaoumi, Marion Descoins, Dominique Mangelinck, Aurelie Gentils
Summary: The properties of oxide dispersion-strengthened steels depend on the nature and size distribution of their nano-oxide precipitates. Experimental results suggest that the formation of these precipitates is not thermodynamically favorable, but rather influenced by the dynamics of the implanted elements and induced defects. The order of ion implantation also affects the characteristics and morphology of the precipitates.
Article
Chemistry, Physical
Lucas Autones, Pascal Aubry, Joel Ribis, Hadrien Leguy, Alexandre Legris, Yann de Carlan
Summary: This study aims to assess the potential of Laser Additive Manufacturing (LAM) for Ferritic/Martensitic ODS steels. The results show that it is difficult to obtain the expected characteristics of F/M ODS grades using LAM processes. The powder melting stage currently limits the possibility of obtaining fine and dense precipitation of nano-oxides in these steels.
Article
Engineering, Mechanical
Gabriel Franck Bouobda Moladje, Ludovic Thuinet, Charlotte S. Becquart, Alexandre Legris
INTERNATIONAL JOURNAL OF PLASTICITY
(2020)
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)
