Article
Nuclear Science & Technology
Yinzhong Shen, Xiaoling Zhou, Xi Huang, Zhijun Fan, Xiaoyu Ma, Hezhou Chen, Xingjian Shi
Summary: The precipitate phases in a reduced activation ferritic/martensitic steel CLAM (HEAT-0912) were observed and analyzed, identifying eight kinds of precipitate phases not previously reported, including Ta-rich MSi2, Ta-rich M3X2, V-rich M2C, and Cr-rich M6C phases.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Materials Science, Multidisciplinary
Xiaochen Zhang, Yinzhong Shen, Mingming Zhang
Summary: The effects of irradiation on the precipitate phases in standard heat-treated CLAM (HEAT-9) steel samples were investigated. Three irradiation-induced phases were identified in the irradiated steel, namely Fe-rich M3C carbide, sigma-FeCr intermetallic compound, and Fe-Cr binary intermetallic compound.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Materials Science, Multidisciplinary
Sheng Yin, Lie Yang, Yuan Liu, Ronggui Yang, Yuanyuan Wang, Fei Zhao
Summary: This study investigated the evolutions of the Laves phase, the M23C6 phase, and the MX phase in CLAM steel during thermal aging. The results showed that the Laves phase exhibited the worst stability and highest coarsening rate among the three phases. The particle size relationship of the Laves phase with time was different from that of the other two phases. The study also observed two nucleation modes and an enwrapping growth mechanism of the Laves phase.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Chemistry, Physical
Maohong Yang, Zheng Zhang, Linping Li
Summary: This paper investigated the evolution of microstructure and microhardness in the G115/Sanicro25 dissimilar steel welded joint during the creep process. The results showed that fracture locations were in the fine-grain heat-affected zone, and the cavities were related to the second phase.
Article
Materials Science, Multidisciplinary
Yue Zhang, Wei Zhang, Li Zeng, Juhua Liang, Jun Xiao, Aimin Zhao
Summary: This study investigated the segregation behavior and precipitates of super-austenitic stainless steel using a thermodynamic calculation and experimental characterization approach. It was found that electromagnetic stirring significantly improved the solidification microstructure and reduced element segregation.
MATERIALS TODAY COMMUNICATIONS
(2022)
Article
Materials Science, Multidisciplinary
Fengjing Wu, Zhonghua Hu, Xiaojuan Liu, Changwei Su, Long Hao
Summary: Previous studies have suggested that the rust layer on plain carbon steels primarily consists of gamma-FeOOH, while that on weathering steels mainly contains alpha-FeOOH. However, this research has found that even after long-term atmospheric exposure, the rust layer on plain carbon steel is still predominantly composed of alpha-FeOOH.
Article
Materials Science, Multidisciplinary
Hossein Alinejad, Majid Abbasi
Summary: The effects of precipitated phases on the magnetic properties of 2304 duplex stainless steel were investigated through various artificial aging treatments. These treatments showed that the presence of precipitates like chromium carbides and chromium nitride decreased the ferrite volume fraction and subsequently led to a decrease in magnetic properties, specifically a decrease in saturation magnetization.
JOURNAL OF MAGNETISM AND MAGNETIC MATERIALS
(2021)
Article
Metallurgy & Metallurgical Engineering
Xin Geng, Xue-ru Tao, Zhou-hua Jiang, Leizhen Peng, Fu-bin Liu, Hua-bing Li
Summary: Microstructure observation and hardness analysis were conducted on 9CrMoCoB steel with different N content during long-term aging at 620 degrees C. The average size of M23C6 phase increased initially and then stabilized after aging for 2,000 hours, while the Laves phase precipitated and coarsened continuously with aging time prolonging. The coarsening rate of the Laves phase remained flat after 2,000 hours. The hardness of the steel decreased gradually with aging time and reached stability after 2,000 hours. The hardness and stability of the steel first increased and then decreased with the increase of N content, reaching maximum at 0.020%. The optimal control range of N content in the steel is around 0.020% to fully utilize the strengthening effect of B and N.
ISIJ INTERNATIONAL
(2023)
Article
Materials Science, Multidisciplinary
H. Wang, A. Kostka, W. E. Goosen, G. Eggeler, J. E. Westraadt
Summary: The study investigated a 12% Cr TMFS after creep testing at high temperature for 139,000 hours, using an extraction replica technique to analyze particle families and explore the chemical evolution of particles. The results were discussed in comparison with previous thin foil data and computational thermodynamics predictions, highlighting the strengths and weaknesses of thin foil and replica procedures, and suggesting improvements for thermodynamic databases.
MATERIALS CHARACTERIZATION
(2021)
Article
Materials Science, Ceramics
Jian Yu, Shifang Ma, Xingxing Xie, Guifu Zhang, Jing Kuang, Luo Qi, Qiongxin Hua, Ping Tang, Wenyu Zhao
Summary: The study showed that BaFe4Sb12 materials exhibit excellent long-term thermal stability due to the unique decomposition layer formed during annealing. The decomposition rate decreases with increasing annealing time, resulting in a protective cover that effectively prevents Sb sublimation. The thermoelectric properties, including the figure of merit, remain stable during the annealing process.
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
(2022)
Article
Energy & Fuels
Laura Quant, Gonzalo Diarce, Lourdes Bouzas, Jean-Pierre Bedecarrats, Ana Garcia-Romero
Summary: The eutectic mixture of urea and sodium nitrate shows promising thermal properties for energy storage, but long-term stability needs further investigation.
SOLAR ENERGY MATERIALS AND SOLAR CELLS
(2021)
Article
Chemistry, Physical
Qiaoli Li, Jin Qin, Daiping Jiang, Danqing Yi, Bin Wang
Summary: This study experimentally and theoretically investigated the precipitate coarsening and property changes of 6082 aluminium alloy after thermal exposure at different temperatures. The results showed that high temperatures caused a decrease in alloy strength and an increase in precipitate size. The Kuehmann-Voorhees model was found to be suitable for calculating the precipitate coarsening rate of the alloy.
JOURNAL OF ALLOYS AND COMPOUNDS
(2022)
Article
Materials Science, Multidisciplinary
Nan Liu, Xitao Wang, Zhenhuan Gao, Jinshan He
Summary: The microstructure stability of directional-solidified MarM247LC alloy was investigated under thermal exposure. The coarsening mechanism and direction of y' phase were found to vary in different regions, and the coarsening rate of y' phase increased significantly with temperature. Additionally, M6C carbides precipitated and underwent distribution change in the alloy.
JOURNAL OF MATERIALS RESEARCH AND TECHNOLOGY-JMR&T
(2023)
Article
Energy & Fuels
Burcu Kocak, Ana Ines Fernandez, Halime Paksoy
Summary: The study confirms that STESM developed from demolition waste demonstrates good thermal and mechanical stability, making it a reliable option for long-term use in solar heat industrial applications.
INTERNATIONAL JOURNAL OF ENERGY RESEARCH
(2021)
Article
Engineering, Civil
Xu Han, Bing Han, Huibing Xie, Wutong Yan, Jiaping Yu, Yikuan He, Longbiao Yan
Summary: This paper analyzes and discusses in detail the effects of long-term behavior on the dynamic strength of CFST arch bridges and proposes a novel dynamic stability analysis method. An existing large-span CFST arch bridge is studied as a case study. The long-term performance evolution of CFST sections is also discussed, emphasizing the significant influence of creep-induced stress on the dynamic stability of arch bridges.
ENGINEERING STRUCTURES
(2022)
Article
Materials Science, Multidisciplinary
L. L. Song, J. F. Li, C. Cai
CORROSION ENGINEERING SCIENCE AND TECHNOLOGY
(2016)
Article
Nuclear Science & Technology
Liangliang Song, Shaojun Liu, Xiaodong Mao
FUSION ENGINEERING AND DESIGN
(2016)
Article
Chemistry, Multidisciplinary
Liang Liang Song, Shaojun Liu, Xiaodong Mao
Article
Materials Science, Multidisciplinary
Chen Hu, Juan-Ding Xiao, Xiao-Dong Mao, Liang-Liang Song, Xin-Yi Yang, Shao-Jun Liu
Article
Materials Science, Multidisciplinary
Liangliang Song, Xinyi Yang, Yanyun Zhao, Wei Wang, Xiaodong Mao
JOURNAL OF NUCLEAR MATERIALS
(2019)
Article
Nuclear Science & Technology
Mengtian Liang, Shaojun Liu, Liangliang Song, Yanyun Zhao
FUSION ENGINEERING AND DESIGN
(2019)
Article
Materials Science, Composites
Chen Hu, Yu-Tao Zhai, Liang-Liang Song, Xiao-Dong Mao
POLYMER COMPOSITES
(2020)
Article
Nuclear Science & Technology
Xinyi Yang, Liangliang Song, Bo Chang, Qi Yang, Xiaodong Mao, Qunying Huang
NUCLEAR MATERIALS AND ENERGY
(2020)
Article
Nuclear Science & Technology
Zhiyuan Xu, Shaojun Liu, Liangliang Song, Xinyi Yang, Yanyun Zhao, Xiaodong Mao
Summary: The study demonstrated that the oxidation resistance of ODS steel is improved with increasing silicon content. The oxide layer and oxides formed during oxidation process varied with different silicon contents, with the silicon-rich oxide layer inhibiting Fe3+ diffusion and increasing the diffusion rate of Cr and Mn. As a result, the addition of Si proved to be beneficial for enhancing the oxidation resistance of ODS steel.
FUSION ENGINEERING AND DESIGN
(2021)
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)
