Article
Nanoscience & Nanotechnology
Lin Deng, Jin-ru Luo, Jian Tu, Rong Hu, Ning Guo, Wen-yu Zeng, Chang-hao Wang, Pei He, Yong Zhang
Summary: As a candidate material for fuel cladding in fission reactors, the mechanical properties of ODS-F/M steel were improved by incorporating ultra-high number density of Y2O3 oxide nanoparticles through the addition of Y2O3 during HIP and optimizing microstructure and properties through hot rolling deformation. The addition of Y2O3 resulted in a bimodal ferrite structure and reticular M23C6 carbides distribution. Following hot rolling, grain size and M23C6 carbides were refined significantly while Y2O3 particle size remained unchanged. This resulted in an excellent combination of strength (1474 MPa) and ductility (13%) in ODS steel prepared by HIP with Y2O3 addition and hot rolling.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
(2023)
Article
Nanoscience & Nanotechnology
Haodong Jia, Ruiqian Zhang, Dijun Long, Yongduo Sun, Zhangjian Zhou
Summary: The aim of this study is to investigate the effect of zirconium content on the mechanical properties of ODS FeCrAl alloys. The results show that adding 0.6 wt% zirconium can achieve the highest number density of dispersed particles and exhibit excellent mechanical properties.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
(2022)
Article
Nanoscience & Nanotechnology
Eddahbi Mohamed Ou Lahcen, Monge Miguel Angel Alcazar, Carvalho Patricia Almeida
Summary: A new improved oxide dispersion strengthened Eurofer steel was produced through a novel two-step mechanical alloying route, resulting in a fully dense material with a microstructure characterized by two distinct zones. The mechanical properties of the processed material were significantly improved compared to various ODS Eurofer and ODS Fe-Cr steels treated by different thermomechanical processing routes, showing softening at 600 degrees C and a steady state constant stress at higher temperatures. Dynamic grain refinement and ferrite to martensite transformation were observed, leading to the formation of low angle grain boundaries.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
(2021)
Article
Chemistry, Physical
Shibo Peng, Jinqiu Hou, Li Yu, Zheng Lu
Summary: ODS AlCrFeNi high entropy alloys were synthesized via mechanical alloying and spark plasma sintering to investigate the effects of sintering temperature and Y2O3/Ti addition on microstructure and hardness. The results showed that the addition of Y2O3 and Ti significantly improved the hardness of the alloy and modified the types of nanoscale oxides present in the microstructure.
Article
Nanoscience & Nanotechnology
Man Wang, Honghong Sun, Baolin Pang, Xiaoli Xi, Zuoren Nie
Summary: In this study, W-Y2O3 alloy was prepared using ball milling and subsequent spark plasma sintering. The microstructure evolution of Y2O3 during the preparation process was characterized in detail. It was found that Y2O3 underwent a transformation from BCC to FCC structure during ball milling and subsequent sintering, and the Y2O3 dispersoids experienced size refinement. The SPSed W-Y2O3 alloy exhibited high compressive strength and microhardness. These properties were attributed to the distribution of nanosized Y2O3 dispersoids inside the grain interior and their semi-coherent relationship with the tungsten matrix.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
(2022)
Article
Nuclear Science & Technology
Bing Ma, Laima Luo, Yoshimitsu Hishinuma, Jing Wang, Yifan Zhang, Hiroyuki Noto, Yucheng Wu, Takeo Muroga
Summary: Reducing the Y2O3 addition from 1.5 wt% to 0.5 wt% investigated the refinement of dispersive Y2O3 particles and exploration of the optimum Y2O3 content for Cu6Y sourced Cu-Y2O3. It was found that reducing the Y2O3 addition had little influence on the number density but reduced the size of the Y2O3 particles. The nucleation point was expected to be more important for the number density of the Y2O3, and reducing the Y2O3 addition improved the mechanical performance and thermal conductivity by thinning the prior particle boundaries with O enrichment and contamination.
NUCLEAR MATERIALS AND ENERGY
(2023)
Article
Chemistry, Physical
Yong-Qiang Qin, Chen-Yu Deng, Bing Ma, Yi-Fan Zhang, Lai-Ma Luo, Yu-Cheng Wu
Summary: In order to address the poor interfacial bonding between the Y2O3 particles and copper matrix in oxide dispersion-strengthened copper, Y4Zr3O12 nanoparticles were prepared and added directly through solid-liquid doping. Characterization by various techniques showed that the interface bonding between Y4Zr3O12 and Cu was superior to that of Y2O3 and Cu. The Cu-3 wt% Y4Zr3O12 composites exhibited the best comprehensive properties, including Vickers hardness, yield strength, ultimate tensile strength, maximum engineering strain, and electrical conductivity. © 2023 Elsevier B.V. All rights reserved.
JOURNAL OF ALLOYS AND COMPOUNDS
(2023)
Article
Engineering, Chemical
Pradyumna Kumar Parida, Arup Dasgupta, Shubhra Bajpai, T. Sakthivel, R. Mythili
Summary: Oxide dispersion strengthened (ODS) steels, containing Ti and Y2O3, show superior mechanical properties and creep-rupture life compared to modified 9Cr-1Mo (P91) steel. Optimizing the Y2O3 and Ti content in ODS steels governs the size and stoichiometry of the dispersoids, with equal amounts of Ti and Y2O3 resulting in finer and stable dispersoids. Two varieties of ODS alloys with different Ti and Y2O3 contents were synthesized and compared with P91 steel in terms of microstructure and microtexture.
Article
Materials Science, Multidisciplinary
Ashwani Kumar, Bhagyaraj Jayabalan, Chetan Singh, Jayant Jain, Subrata Mukherjee, Krishanu Biswas, Sudhanshu S. Singh
Summary: In this study, lanthana based oxide dispersion strengthened ferritic steels were fabricated and the effects of chromium content and sintering temperature on the mechanical properties were investigated. The results showed that increasing the chromium content improved the compressive strength and compressive fracture strain of the steel.
METALS AND MATERIALS INTERNATIONAL
(2023)
Article
Chemistry, Physical
Li Yu, Zheng Lu, Jiabei Xian, Xuanyu Chen, Shibo Peng, Xiaolong Li, Hui Li
Summary: Two kinds of Ni-based oxide dispersion strengthening (ODS) superalloys with high/low Al contents were investigated for their microstructure and tensile property. ODS-HA is strengthened by both Ni3Al precipitates and nanoscale oxides, while ODS-LA is strengthened mainly by nanoscale oxides. The type and size of nanoscale oxides depend on the Al content. High Al content results in increased tensile strength and decreased ductility.
JOURNAL OF ALLOYS AND COMPOUNDS
(2023)
Article
Nanoscience & Nanotechnology
You Wu, Haozhi Zhao, Jikang Li, Yuanyuan Zhang, Tong Liu
Summary: The addition of Y4Zr3O12 nanoparticles improved the mechanical properties of ODS steels, particularly enhancing the uniform elongation. This improvement was attributed to the formation of homogeneous oxide NPs and the strong bonding force of the coherent interface.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
(2021)
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, Ceramics
Ruoyu Chen, Adam Bratten, Joshua Rittenhouse, Haiming Wen
Summary: The use of mechanically alloyed Al2O3-Y2O3 mixtures as sintering additives can promote liquid phase sintering of SiC, but prolonged ball milling time results in an excessive volume of complex oxide phases in the sintered specimens, negatively affecting the mechanical properties of SiC specimens.
CERAMICS INTERNATIONAL
(2022)
Article
Materials Science, Multidisciplinary
Shibo Peng, Zheng Lu, Li Yu
Summary: This study prepared oxide dispersion strengthened (ODS)-CrFeNi medium entropy alloys (MEAs) with different amounts of Y2O3/Zr using mechanical alloying (MA) and spark plasma sintering (SPS), and investigated the influence of Y2O3/Zr amounts on microstructure and mechanical properties. The results showed that the Y2O3/Zr amounts affected the grain size, hardness, and formation of different phases in the alloys.
MATERIALS CHARACTERIZATION
(2022)
Article
Materials Science, Multidisciplinary
Jaroslaw J. Jasinski, Tomasz Stasiak, Wojciech Chmurzynski, Lukasz Kurpaska, Marcin Chmielewski, Malgorzata Frelek-Kozak, Magdalena Wilczopolska, Katarzyna Mulewska, Maciej Zielinski, Marcin Kowal, Ryszard Diduszko, Witold Chrominski, Jacek Jagielski
Summary: This study presents a novel research path for developing FeCrAl matrix ODS steels with Y2O3, Ti, and V additions. The addition of vanadium improves the hardness of the material, and the presence of nanoscale oxide particles in the matrix enhances its radiation damage resistance.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Nuclear Science & Technology
P. Unifantowicz, Z. Oksiuta, P. Olier, Y. de Carlan, N. Baluc
FUSION ENGINEERING AND DESIGN
(2011)
Article
Engineering, Electrical & Electronic
J. B. Dubois, L. Thilly, F. Lecouturier, P. Olier, P. O. Renault
IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY
(2012)
Article
Materials Science, Multidisciplinary
Z. Oksiuta, P. Olier, Y. de Carlan, N. Baluc
JOURNAL OF NUCLEAR MATERIALS
(2009)
Article
Materials Science, Multidisciplinary
Y. de Carlan, J. -L Bechade, P. Dubuisson, J. -L. Seran, P. Billot, A. Bougault, T. Cozzika, S. Doriot, D. Hamon, J. Henry, M. Ratti, N. Lochet, D. Nunes, P. Olier, T. Leblond, M. H. Mathon
JOURNAL OF NUCLEAR MATERIALS
(2009)
Article
Materials Science, Multidisciplinary
P. Oiler, J. Malaplate, M. H. Mathon, D. Nunes, D. Hamon, L. Toualbi, Y. de Carlan, L. Chaffron
JOURNAL OF NUCLEAR MATERIALS
(2012)
Article
Materials Science, Multidisciplinary
L. Toualbi, C. Cayron, P. Olier, J. Malaplate, M. Praud, M. -H. Mathon, D. Bossu, E. Rouesne, A. Montani, R. Loge, Y. de Carlan
JOURNAL OF NUCLEAR MATERIALS
(2012)
Article
Materials Science, Multidisciplinary
P. Olier, M. Couvrat, C. Cayron, N. Lochet, L. Chaffron
JOURNAL OF NUCLEAR MATERIALS
(2013)
Article
Materials Science, Multidisciplinary
L. Toualbi, C. Cayron, P. Olier, R. Loge, Y. de Carlan
JOURNAL OF NUCLEAR MATERIALS
(2013)
Article
Nanoscience & Nanotechnology
L. Waltz, D. Retraint, A. Roos, P. Olier
SCRIPTA MATERIALIA
(2009)
Article
Materials Science, Coatings & Films
L. Waltz, D. Retraint, A. Roos, C. Garnier, P. Olier
SURFACE & COATINGS TECHNOLOGY
(2011)
Article
Engineering, Manufacturing
E. Buet, J. B. Dubois, P. Olier, L. Thilly, F. Lecouturier, P. O. Renault
INTERNATIONAL JOURNAL OF MATERIAL FORMING
(2010)
Article
Engineering, Manufacturing
Emilien Buet, Jean-Baptiste Dubois, Patrick Olier, Ludovic Thilly, Florence Lecouturier, Pierre-Olivier Renault
INTERNATIONAL JOURNAL OF MATERIAL FORMING
(2012)
Article
Materials Science, Multidisciplinary
Emilien Curtet, Bouzid Kedjar, Frederic Mompiou, Hadi Bahsoun, Frederic Pailloux, Arnaud Courcelle, Matthew Bono, Patrick Olier, Ludovic Thilly
Proceedings Paper
Materials Science, Characterization & Testing
J. C. Brachet, P. Olier, V. Vandenberghe, S. Doriot, S. Urvoy, D. Hamon, T. Guilbert, A. Mascaro, J. Jourdan, C. Toffolon-Masclet, M. Tupin, B. Bourdiliau, C. Raepsaet, J. M. Joubert, J. L. Aubin
ZIRCONIUM IN THE NUCLEAR INDUSTRY
(2015)
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)