Article
Materials Science, Multidisciplinary
Pratish R. Rao, Krishna Muralidharan, Moe Momayez, Keith Runge
Summary: This study focuses on microstructural characterization of silica-alumina foam with controllable porosity, revealing the closed cell structure and compositional features. The presence of a crystalline 'film' phase NaAlSiO4 is observed in close proximity to inorganic particles, which is hypothesized to act as a binder phase between silica particles. Increasing foam density leads to a decrease in the ratio of average pore-size to average strut thickness, while SEM data indicate that SAF foams exhibit a hierarchical pore structure.
MATERIALS CHARACTERIZATION
(2021)
Article
Crystallography
Sunder Jebarose Juliyana, Jayavelu Udaya Prakash, Sachin Salunkhe, Hussein Mohamed Abdelmoneam Hussein, Sharad Ramdas Gawade
Summary: Hybrid composites, such as aluminum matrix composites strengthened with ceramic particulates, are widely used in marine, aerospace, and defense applications for their exceptional properties. Zirconia-reinforced composites and graphite composites are preferred for their high refractory properties, abrasion resistance, and lightweight for applications like spacecraft parts and racecars. The addition of reinforcement like zirconia and graphite in metal matrix composites enhances hardness, impact, and compressive strength.
Article
Engineering, Geological
Hongdan Yu, Chen Lu, Weizhong Chen, Diansen Yang, Honghui Li
Summary: In this study, the physical characteristics and microstructural features of Tamusu mudstone in western Inner Mongolia were characterized using various analytical techniques. The results revealed diverse mineral compositions, complex pore structures, and varying pore sizes in the mudstone.
JOURNAL OF ROCK MECHANICS AND GEOTECHNICAL ENGINEERING
(2022)
Article
Materials Science, Multidisciplinary
J. David Arregui-Mena, Philip D. Edmondson, David Cullen, Samara Levine, Cristian Contescu, Yutai Katoh, Nidia Gallego
Summary: In the 1960s, the feasibility of molten salt reactors for civil applications was demonstrated by the Molten Salt Reactor Experiment using CGB graphite as the fast neutron moderator. Additional impregnation steps were taken to reduce molten salt ingression, but little information has been published about the microstructure or sealant of this graphite grade. The study presents advanced microscopy results and investigates the sealing technology of legacy material from the Molten Salt Reactor Experiment, providing insights for potential reutilization in modern reactors.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Engineering, Chemical
Won Jung Cho
Summary: The present study investigated the potential use of ferronickel slag (FNS) in ternary mix for cementitious material in concrete mix. The reactivity of FNS-ternary mix in the cement matrix was observed experimentally, and the performance of the concrete/mortar was simultaneously tested. The results showed that the FNS-ternary mix delayed the hydration process beyond 90 days, slightly reducing the development of compressive strength, but it promoted the formation of a denser pore structure, leading to more durable concrete. The economic and environmental benefits make the application of FNS-ternary mix feasible for in-situ use.
Article
Construction & Building Technology
Shiwei Yu, Ming Xia, Jay Sanjayan, Lin Yang, Jianzhuang Xiao, Hongjian Du
Summary: This study investigates the microstructural characterization of 3D printed concrete using MIP and X-ray CT, revealing that the presence of more macropores and large voids in the samples, leading to lower strength compared to mould-cast specimens. The morphology of voids in the 3D printed samples is also found to be more irregular and elongated, particularly at the interlayer.
JOURNAL OF BUILDING ENGINEERING
(2021)
Article
Materials Science, Multidisciplinary
Steve Johns, Timothy Yoder, Karthik Chinnathambi, Rick Ubic, William E. Windes
Summary: This study found that thermal annealing of nuclear graphite at 2500 degrees C can lead to the formation of fullerene-like defects, which may directly contribute to the non-recoverable physical property changes observed in irradiated nuclear graphites.
MATERIALS CHARACTERIZATION
(2022)
Article
Construction & Building Technology
Yanming Liu, Shu Jian Chen, Kwesi Sagoe-Crentsil, Wenhui Duan
Summary: In this study, a digital concrete model was used to analyze the pore structure of cement, showing promising results for future research. The model provided a new approach to studying the microstructural properties of cementitious materials and has the potential to transform traditional analytical processes.
CONSTRUCTION AND BUILDING MATERIALS
(2021)
Article
Geosciences, Multidisciplinary
Gabriel C. Unomah, Manika Prasad, Michael A. Oladunjoye, Idowu A. Olayinka
Summary: This study investigates the geological properties of the Lokpanta Shale in the Anambra Basin and identifies its potential as an unconventional hydrocarbon resource. The study findings suggest that the shale contains organic matter and clay minerals, with wide pore distribution and high fluid storage, transport, and adsorption capacity.
MARINE AND PETROLEUM GEOLOGY
(2022)
Article
Materials Science, Multidisciplinary
Jose David Arregui-Mena, Robert N. Worth, William Bodel, Benjamin Maerz, Wenjing Li, Anne A. Campbell, Ercan Cakmak, Nidia Gallego, Cristian Contescu, Philip D. Edmondson
Summary: This article presents a detailed examination of the heterogeneity, microstructure, and pore structure of different graphite grades and their binder and filler phases using various microscopy and analytical techniques. Significant differences were found between coarser and finer grades, and a framework for assessing materials is proposed.
MATERIALS CHARACTERIZATION
(2022)
Article
Chemistry, Inorganic & Nuclear
Jordan F. Corbey, Lucas E. Sweet, Sergey Sinkov, Dallas D. Reilly, Cyrena M. Parker, Jason M. Lonergan, Timothy J. Johnson
Summary: This study presents a comprehensive analysis of time-resolved powder X-ray diffraction experiments, solid-state optical spectroscopy, and electron microscopy of aged plutonium oxalate powders. The data provide new insights into the chemical and structural changes that occur in these solids over time at room temperature, suggesting the auto-decomposition of plutonium oxalates to form nanocrystalline plutonium oxide.
EUROPEAN JOURNAL OF INORGANIC CHEMISTRY
(2021)
Article
Green & Sustainable Science & Technology
Minghao Dong, Shaoqin Ruan, Shulin Zhan, Siyi Shen, Guangcheng Sun, Xiaoqian Qian, Xiangming Zhou
Summary: This study finds that using red mud in autoclaved aerated concrete can reduce its radiation and environmental pollution. Although the introduction of red mud has some drawbacks, it can alleviate drying shrinkage and promote the formation of tobermorite.
JOURNAL OF CLEANER PRODUCTION
(2022)
Article
Construction & Building Technology
Hongqiang Ma, Xiaoyan Niu, Jingjing Feng
Summary: The property and microstructural evolutions of MgO-slag cementitious materials at different temperatures were comprehensively evaluated in this study. The results demonstrate that the materials have good high-temperature resistance, and the formation of brucite is related to the compressive strength changes.
JOURNAL OF BUILDING ENGINEERING
(2022)
Article
Materials Science, Multidisciplinary
Yanming Liu, Shu Jian Chen, Kwesi Sagoe-Crentsil, Wenhui Duan
Summary: This study focused on the detailed microstructural analysis of the hydration process of C3S, a simplified model of cementitious material. It was found that the length of a metastable barrier in the BSE images correlated well with the hydration rate of C3S, and the hydration process caused significant changes in the pore size and profile of C3S pastes, with the critical pore size for limiting hydration identified as 4 μm. Additionally, C3S samples were observed to reach 80% hydration at 7 days, with continuous development of pore structure thereafter despite similar porosity and hydration levels.
MATERIALS CHARACTERIZATION
(2021)
Article
Energy & Fuels
Jiajia Liu, Zishuo Nie, Yuanlong Li, Ming Yang, Yunlong Zhang
Summary: This paper proposed a microstructural analysis for coal-rock based on low-field nuclear magnetic resonance (LNMR) technology, the L-weighing method, to accurately and quantitatively characterize the evolution of coal microstructures before and after supercritical CO2 treatment. The experimental results of the L-weighing method and the LNMR method were compared and analyzed, and it was found that there were differences between the two methods but the overall laws were basically the same. The L-weighing method quantitatively characterizes the water content in coal and determines water consumption and microscopic component extraction in coal with supercritical CO2, while the LNMR method only determines the dissolution of H-containing substances in the coal by supercritical CO2. According to the combined analysis with the L-weighing method and the LNMR method, it was found that the supercritical CO2 treatment led to water consumption, extraction of microscopic components, volume expansion, permeability increase, and pore connectivity increase in the coal microstructure.
Article
Materials Science, Ceramics
Evan Smith, Claire Adams, Rick Ubic
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2020)
Article
Nuclear Science & Technology
H. D. Gougar, D. A. Petti, P. A. Demkowicz, W. E. Windes, G. Strydom, J. C. Kinsey, J. Ortensi, M. Plummer, W. Skerjanc, R. L. Williamson, R. N. Wright, D. Li, A. Caponiti, M. A. Feltus, T. J. O'Connor
NUCLEAR ENGINEERING AND DESIGN
(2020)
Article
Chemistry, Physical
Joshua J. Kane, Austin C. Matthews, W. David Swank, William E. Windes
Article
Chemistry, Physical
Dong Liu, David Cherns, Steve Johns, Yan Zhou, Junliang Liu, Wei-Ying Chen, Ian Griffiths, Chinnathambi Karthik, Meimei Li, Martin Kuball, Joshua Kane, William Windes
Summary: The study found a vein structure on the surface of highly oriented pyrolytic graphite (HOPG) that became more pronounced with increasing ion dose, independent of crystallographic orientations and associated with the formation of pores. A triangular-shaped core was formed underneath the veins, generating a macro-scale 'ruck&tuck' geometry. The progressive movement of dislocations along basal planes during irradiation was observed, and a mechanistic model was proposed to explain vein formation and dimensional changes in graphite materials.
Article
Materials Science, Multidisciplinary
R. E. Smith, J. J. Kane, W. E. Windes
Summary: This study compared the acute oxidation behaviors of various nuclear graphite grades relevant to gas-cooled high-temperature reactor designs using established ASTM oxidation testing standards. It was found that graphite components in the HTR core region are expected to oxidize in the event of air-ingress, leading to potential mass loss. The research also discussed the effects of high impurity levels on oxidation performance among different grades.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Lingfeng He, Marat Khafizov, Chao Jiang, Beata Tyburska-Puschel, Brian J. Jaques, Pengyuan Xiu, Peng Xu, Mitchell K. Meyer, Kumar Sridharan, Darryl P. Butt, Jian Gan
Summary: In this study, the phase and defect evolution under proton irradiation in a nitride-oxide composite using a model system of 5 wt.% uranium dioxide (UO2) in uranium mononitride (UN) was investigated. Proton irradiation at elevated temperatures promoted the transformation of UN into uranium sesquinitride (U2N3) and UO2 phases, forming a fully coherent structure. The growth of dislocation loops was observed, with the loop size being larger in nitride phases than in UO2 and the loop density being higher in UO2 than in nitride phases. Kinetic rate theory was used for analyzing loop density and diameter, leading to the conclusion that loop growth is governed by the mobility of uranium interstitials in all compounds. The study provides insights into the early stage of microstructure evolution under irradiation, with implications for the use of this mixture as advanced fuel in nuclear energy systems.
Article
Chemistry, Physical
Rakesh Batchu, Zachary Thompson, Zongtang Fang, William E. Windes, Eric J. Dufek, Rebecca R. Fushimi
Summary: Quantification of oxidation kinetics is crucial for developing graphitic materials for various applications, and experiments using highly oriented pyrolytic graphite have revealed the role of surface diffusion and quantified oxidation kinetics with nanomole-precision. An unexpected increase in reactivity following annealing was observed, explained by the role of surface diffusion in trapping mobile oxygen at more reactive edge sites. The unique time-resolved non-equilibrium measurement in a well-defined transport regime enabled observation of short-term deactivation, reactivity increases due to surface diffusion, and longer-term reactivity increase with oxygen accumulation.
Article
Nuclear Science & Technology
Austin C. Matthews, Joshua J. Kane, W. David Swank, William E. Windes
Summary: This study determined the oxidized residual strength of two nuclear graphite grades at different oxidation temperatures, addressing the critical licensing issue within the ASME Boiler Pressure and Vessel Code. Results showed that low-temperature oxidation resulted in a greater strength reduction compared to higher temperatures, depending on whether oxidation occurred in the kinetic-controlled regime or diffusion- controlled regime. A new test method combining ASTM standards was also presented to aid in determining oxidized residual strength for ASME BPVC users.
NUCLEAR ENGINEERING AND DESIGN
(2021)
Article
Nuclear Science & Technology
Vishal Patel, Jorge Navarro, William Windes, Pavel Tsvetkov
Summary: In material test reactor calculations, uncertainties in energy dependent flux and reaction rates are often not quantified. High fidelity Monte-Carlo codes lack straightforward methods to calculate output uncertainties, relying on expert opinions instead. New methods for propagating uncertainties through simulations are available with sufficient computational power.
ANNALS OF NUCLEAR ENERGY
(2022)
Editorial Material
Physics, Applied
Nathan D. Orloff, Rick Ubic, Michael Lanagan
APPLIED PHYSICS LETTERS
(2022)
Article
Energy & Fuels
Jiaqi Jin, Chen-Luh Lin, Shoeleh Assemi, Jan D. Miller, Darryl P. Butt, Taylor Jordan, Milind D. Deo, Viktoriya Semeykina
Summary: The study simulated fluid flow through nanopore structures using pressure-assembled colloidal silica spheres and characterized them using X-ray computed tomography. The nanopore networks exhibited pore size distributions corresponding to the particle sizes, but the simulated permeability was lower than experimental values, highlighting the need to consider the complex packing and surface chemistry issues of silica spheres in future research.
JOURNAL OF PETROLEUM SCIENCE AND ENGINEERING
(2022)
Article
Materials Science, Multidisciplinary
Z. Wang, O. Muransky, H. Zhu, T. Wei, Z. Zhang, M. Ionescu, C. Yang, J. Davis, G. Hu, P. Munroe, W. Windes
Summary: The ion irradiation-induced microstructural changes in a carbon-fibre reinforced carbon-matrix (C/C) composite were investigated using Raman spectroscopy. It was found that the high concentration of pre-existing crystal lattice defects in the C/C composite had a significant impact on the disordering of the crystal lattice. In contrast, graphite with fewer pre-existing defects behaved in a more predictable manner. The results suggest the importance of eliminating crystal lattice defects in the as-manufactured microstructure of C/C composites for radiation-tolerant applications. Additionally, the study identified a knowledge gap regarding the electronic energy loss effect on ion irradiation damage in carbon-based materials at intermediate ion energies.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Materials Science, Multidisciplinary
Gongyuan Liu, Yichun Tang, Khalid Hattar, Yuzhou Wang, William Windes, Aman Haque, Jing Du
Summary: This study aims to establish an experimental method to investigate pre-existing defects and 3-D crack growth inside nuclear graphite. Three-point bending tests were performed on specimens with and without micro-CT. The results highlight the capability of laboratory micro-CT-based experimental method for the visualization of multi-scale defect interactions, which remains to be a challenge in the characterization of nuclear graphite.
JOURNAL OF MATERIALS RESEARCH
(2023)
Article
Materials Science, Multidisciplinary
Steve Johns, William E. Windes, David T. Rohrbaugh, David L. Cottle
Summary: Previous research has demonstrated that the properties of nuclear grade graphite are significantly influenced by atomic and microstructural changes caused by neutron irradiation. Factors such as irradiation dose, temperature, graphite composition, and initial microstructure play a role in these changes. Understanding the mechanisms and nature of these material changes can facilitate predicting property changes based on these variables. Other studies have shown that these atomic and microstructural changes can be reversed by heating the irradiated graphite above its irradiation temperature. This study investigates the recovery of irradiated graphite properties when heated, providing insight into the damage caused by neutron irradiation. The presented data shows the recovery of thermal diffusivity, coefficient of thermal expansion, Young's modulus, and electrical resistivity between annealing temperatures of 500 degrees C and 2380 degrees C. Graphite grades NBG-18, IG-110, and PCEA are considered, both stressed and unstressed during irradiation.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Nuclear Science & Technology
Josina W. Geringer, Y. Katoh, S. Gonczy, T. Burchell, M. Mitchell, M. Jenkins, W. E. Windes
Summary: Fiber-reinforced ceramic matrix composites have excellent thermal and mechanical properties, making them attractive for high-temperature nuclear applications. These composites have also expanded to commercial non-nuclear industries in the past 20 years due to advancements in fabrication and application technologies. The ASME Boiler Pressure Vessel Code provides design and construction rules for High Temperature Reactor components, including the recently published rules for ceramic matrix composites. These rules outline quality requirements, design methodologies, and material criteria for the use of silicon carbide- and carbon-based matrix materials.
NUCLEAR ENGINEERING AND DESIGN
(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)
