Article
Nuclear Science & Technology
Suvendu Kumar Barik, Abhiram Senapati, S. Balakrishnan, K. Ananthasivan
Summary: Sodium aluminium phosphate (NAP) glass has been found to be an optimal choice for immobilizing minor actinides. The addition of rare-earths and Al2O3 significantly modifies the structure of the glass. Increasing dopant concentration improves the glass's melting point, glass transition temperature, and thermal stability, while decreasing its fragility. The addition of rare-earths enhances the strength of the glass up to a certain concentration, beyond which the rigidity of the structure decreases.
PROGRESS IN NUCLEAR ENERGY
(2022)
Article
Materials Science, Ceramics
Mohamed M. El-Sayed Seleman, A. A. El-Kheshen, Mohamed F. Raslan, Rasha H. Shoeir
Summary: Research in nuclear mining industries focuses on separating heavy and radioactive minerals from rocks and sediments. One method involves using borosilicate glass to immobilize nuclear waste, resulting in a durable glass with low radiation levels that can safely be used for waste immobilization.
CERAMICS INTERNATIONAL
(2022)
Article
Materials Science, Ceramics
Guilin Wei, Xiaoyan Shu, Mingfen Wen, Yuexiang Lu, Tao Duan, Shunzhang Chen, Hexi Tang, Jing Chen, Faqin Dong, Yi Xie, Yang He, Xirui Lu
Summary: This study investigates the mechanism of nuclear waste immobilization using Gd2Zr2O7 ceramic, demonstrating that high sintering temperature promotes transformation and increases chemical stability of the matrices for radioactive waste.
CERAMICS INTERNATIONAL
(2022)
Article
Materials Science, Ceramics
D. C. Lago, A. D. Sanchez, M. O. Prado
Summary: This article experimentally explores the immobilization of high-level waste using sintering in yttrium aluminosilicate glass. A waste form with 10% waste loading was successfully produced through chemical and thermal processes. The sintering process was characterized using mass spectrometry, and the final product exhibited a porous vitroceramic structure. XRD and SEM/EDS mappings were used to analyze the crystalline phases and distribution of the waste. The aqueous corrosion resistance of the waste form was found to be better than borosilicate glasses used in nuclear waste immobilization.
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
(2022)
Article
Materials Science, Ceramics
Yi Ding, Weijie Fan, Zhenyu Chen, Zhen Li, Yuan Liu, Hui Dan, Tao Duan
Summary: Mesoporous ZrO2/SBA-15 was utilized for efficient enrichment and immobilization of uranium in radioactive wastewater. The enriched uranium was transformed into stable ZrSiO4-U ceramics through sintering, demonstrating good aqueous durability. This material shows promise for actual applications in treating U-containing radioactive wastewater due to its high adsorption capacity and durability.
CERAMICS INTERNATIONAL
(2021)
Review
Materials Science, Multidisciplinary
Yingjie Zhang, Anamul H. Mir
Summary: Brannerite structured materials have gained recent attention as waste forms for uranium-rich radioactive wastes. The synthesis, crystal chemistry, polymorphism, uranium valence states, vibrational modes, chemical durability, and radiation damage of brannerite have been investigated. In addition to full ceramics, brannerite based glass-ceramic composites have been developed for waste forms. This review covers the latest advances in brannerite structured materials, focusing on synthesis, structures and spectroscopies, waste form design strategies, processing techniques, and performance studies.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Materials Science, Ceramics
Guilin Wei, Fen Luo, Yulong Miao, Wenhong Han, Yi Xie, Wenxiao Huang, Zhengfan Xu, Xirui Lu
Summary: This study successfully immobilized different types of simulated zeolite wastes under suitable experimental conditions, with a sintering temperature of 1500 degrees Celsius and a holding time of 1 hour. The main microstructures were identified as sheet silicates through FT-IR results, and SEM-EDS results confirmed the formation of a glass-ceramic matrix to effectively immobilize the considered nuclear wastes.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2022)
Article
Materials Science, Ceramics
Kimbal T. Lu, Yingjie Zhang, Tao Wei, Gabriel L. Murphy, Aurpa Bhuiyan, Nicholas Scales, Rongkun Zheng
Summary: This study presents a comprehensive investigation on lanthanide monouranate-based glass-ceramic composites as potential waste forms for the immobilization of lanthanide actinide fraction waste. The results show that the crystalline LnUO(4) precursor can be well stabilized in a sodium aluminoborosilicate glass, while the in situ crystallization of EuUO4 from oxide precursors is robust under various processing conditions. Microscopic observations reveal different microstructures, and diffuse reflectance spectroscopy confirms the presence of pentavalent uranium.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2022)
Article
Engineering, Environmental
Chenna Rao Borra, Thijs J. H. Vlugt, Yongxiang Yang, Jeroen Spooren, Peter Nielsen, Murugaiyan Amirthalingam, S. Erik Offerman
Summary: This study successfully recovered rare earth oxides from waste polishing materials to produce high-value Al-La-Ce alloys. The development of new alloys through novel processes helps utilize both overproduced primary rare earth oxides and those recovered from waste materials.
RESOURCES CONSERVATION AND RECYCLING
(2021)
Article
Materials Science, Ceramics
Haifeng Liu, Hua Wang, Jian Zhao, Jie Li, Xingquan Zhang, Jiacheng Yang, Yongchang Zhu, Ruishi Xie, Kui Zheng, Heyan Huang, Jichuan Huo
Summary: The article presents a method for immobilizing radioactive Cs and Sr simultaneously at low temperatures, and develops a suitable host phase. By fixing the polycrystalline powders in a glass matrix, glass/ceramic composite waste forms with low porosity, good compactness, and high hardness are obtained.
CERAMICS INTERNATIONAL
(2022)
Article
Nuclear Science & Technology
Miae Kim, Jaehyuk Kang, Jang-Hee Yoon, Sang-Geul Lee, Wooyong Um, Hyun Gyu Kim
Summary: This study revealed the partitioning effect and corrosion mechanism of oxyapatite glass-ceramics under different corrosion conditions, confirming their potential in the immobilization of rare-earth radioactive nuclides.
NUCLEAR ENGINEERING AND TECHNOLOGY
(2022)
Article
Materials Science, Multidisciplinary
B. Y. Zhen-Wu, D. P. Prentice, D. Simonetti, J. Ryan, G. Sant, M. Bauchy
Summary: This study predicts the stability of secondary phases upon the dissolution of nuclear waste immobilization glasses through geochemical modeling, revealing different thermodynamic stabilities of secondary phases under different pH conditions. The findings suggest that thermodynamics may play a crucial role in determining the occurrence of Stage III corrosion during nuclear waste disposal.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Chemistry, Physical
Yucheng Liu, Guobiao Li, Dong Wang, Zhenchen Zhong, Kaibo Hu, Chuanqi Zhang, Guoping Hu, Xuewei Li, Yinhua Wan
Summary: In this study, a high value-added near-infrared glass-ceramic photocatalyst was synthesized by replacing pure fluoride with fluorine-containing waste. The photocatalyst exhibited efficient photocatalytic degradation and stability, and it was also regenerable. This study provides references for the high value-added utilization of fluorine-containing waste.
JOURNAL OF COLLOID AND INTERFACE SCIENCE
(2023)
Article
Chemistry, Physical
Yanqing Fu, Shiliang Kang, Shangsheng Guan, Gangjie Zhou, Saihui Li, Linling Tan, Changgui Lin
Summary: Transparent oxyfluoride glass ceramics containing NaYF4: Er3+/Ho3+/Dy3+ nanocrystals were successfully prepared, showing enhanced and broadband mid-infrared emission at 2.5-3.3 μm. The optical properties of the GCs make them promising for potential applications in MIR broadband tunable lasers.
JOURNAL OF ALLOYS AND COMPOUNDS
(2022)
Article
Materials Science, Multidisciplinary
D. C. Lago, A. D. Sanchez, M. O. Prado
Summary: The immobilization of Cs-137 serves different purposes, such as reducing thermal loading of glass and increasing waste loading capacity, as well as producing radioactive sealed sources for industrial and medical applications. Spent nuclear fuel is the most important radioactive waste in the nuclear fuel cycle. Vitrification is the main technology used to immobilize these wastes, providing structural stability, thermal shock resistance, and high chemical durability.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Chemistry, Physical
Rajan Saini, Saurabh Kapoor, Daniel R. Neuville, Randall E. Youngman, Bianca M. Cerrutti, John S. McCloy, Hellmut Eckert, Ashutosh Goel
Summary: This study focuses on the relationship between the solubility of sulfur (as SO3) and the structure of Na2O-B2O3-SiO2 glasses. The research found an inverse correlation between the sulfur solubility and the degree of network polymerization in the glasses. While the modification of SO3 can compete with depolymerization mechanisms, the conversion of BO3 to BO4 induced by alkali cations is dominant. These findings have important implications for understanding the control of sulfur solubility in borosilicate-based nuclear waste glasses.
JOURNAL OF PHYSICAL CHEMISTRY C
(2022)
Article
Spectroscopy
Samuel Karcher, Ritesh Mohun, Travis Olds, Marc Weber, Kyle Kriegsman, Xiaodong Zhao, Xiaofeng Guo, Claire Corkhill, David Field, John McCloy
Summary: This paper presents the application of Raman spectroscopy in the study of the structure of UO2 and its changes due to various factors. By utilizing different excitation wavelengths, the effects of doping, irradiation, heating, and oxidation can be assessed. The combination of Raman maps and electron backscatter diffraction allows for correlative microscopy and the investigation of structural rearrangement.
JOURNAL OF RAMAN SPECTROSCOPY
(2022)
Article
Materials Science, Ceramics
Nikhila Balasubramanya, Zhenxuan Sun, Mostafa Ahmadzadeh, Saeed Kamali, Daniel R. Neuville, John S. McCloy, Ashutosh Goel
Summary: Spinel crystallization can negatively affect the operation of ceramic melters during nuclear waste vitrification. Existing methods to tackle this issue include designing compositions and developing empirical models to predict spinel settling behavior. However, these methods have limitations and further research on chemo-structural descriptors controlling crystallization behavior is needed.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2022)
Article
Chemistry, Physical
Shichao Ding, Zhaoyuan Lyu, Erik Sarnello, Mingjie Xu, Lingzhe Fang, Hangyu Tian, Sam Ellery Karcher, Tao Li, Xiaoqing Pan, John McCloy, Guodong Ding, Qiang Zhang, Qiurong Shi, Dan Du, Jin-Cheng Li, Xiao Zhang, Yuehe Lin
Summary: In this study, a MnOx engineered Fe-N-C single-atom catalyst (Mn-Fe-N-C SAC) was developed to reduce oxidative corrosion and enhance the stability of the oxygen reduction reaction (ORR). The Mn-Fe-N-C SAC exhibited ultralow H2O2 yield and negligible potential shift after continuous potential cycles, demonstrating excellent ORR stability and improved activity compared to common Fe-N-C SACs. The interaction between MnOx and Fe-N-x sites enhanced the intrinsic activity of single iron sites, providing a promising solution for the stability issue of Fe-N-C SACs while maintaining high catalytic activity.
JOURNAL OF MATERIALS CHEMISTRY A
(2022)
Article
Chemistry, Inorganic & Nuclear
Lewis R. Blackburn, Luke T. Townsend, Sebastian M. Lawson, Amber R. Mason, Martin C. Stennett, Shi-Kuan Sun, Laura J. Gardner, Ewan R. Maddrell, Claire L. Corkhill, Neil C. Hyatt
Summary: This study comprehensively investigates the incorporation of Dy3+ in the zirconolite solid solution, revealing different phase structures at varying Dy concentrations. The presence of Dy as Dy3+ in the zirconolite matrix, similar to Am3+, was confirmed. Furthermore, the study demonstrates that the addition of Dy leads to the formation of zirconolite-4M and pyrochlore polytype phases.
INORGANIC CHEMISTRY
(2022)
Article
Materials Science, Ceramics
Jose Marcial, Maria Rita Cicconi, Carolyn Pearce, Jaroslav Klouzek, James J. Neeway, Richard Pokorny, Miroslava Vernerova, John S. McCloy, Emily T. Nienhuis, Rolf Sjoblom, Jamie L. Weaver, Russell J. Hand, Pavel Hrma, Daniel R. Neuville, Albert A. Kruger
Summary: This study investigated the melting behavior, glass transition temperature, oxidation state, network structure, and chemical durability of 1500-year-old vitrified hillfort glasses. The results showed that the oxidation state of iron affected the network connectivity of the glass-forming melt, but it did not affect the chemical durability of the final glass. Glasses with lower network connectivity had lower viscosity and transition temperature.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2023)
Article
Crystallography
Rubi Gul, John Stuart McCloy, Magesh Murugesan, Benjamin Montag, Jasdeep Singh
Summary: In this study, Cl-doped CdTe single crystals were grown under tellurium excess conditions, and the effects of tellurium excess on detector performance and resistivity were investigated. The results showed that tellurium excess caused additional nucleation and decreased grain size, but also improved electrical transport properties. Furthermore, Cl-doped CdTe crystals grown under 15% tellurium excess exhibited better response to gamma rays and alpha particles, as well as high electron and hole mobilities.
Article
Engineering, Electrical & Electronic
Syeed E. Ahmed, Violet M. Poole, Jani Jesenovec, Benjamin L. Dutton, John S. McCloy, Matthew D. McCluskey
Summary: Annealing Ba1-xCaxTiO3 (BCTO) under a flowing humid 2% hydrogen-argon gas mixture results in room-temperature persistent photoconductivity (PPC). This is attributed to the presence of substitutional hydrogen impurities that can be photoexcited. The threshold photon energy for PPC in BCTO is lower than that of BaTiO3 and SrTiO3, and the effect is reversible upon annealing in air.
JOURNAL OF ELECTRONIC MATERIALS
(2023)
Article
Materials Science, Ceramics
Natalie Smith-Gray, Nicholas Stone-Weiss, Sam Karcher, Jonathan Evarts, Jessica Sly, John Bussey, John McCloy
Summary: During vitrification, the presence of sulfur can lead to the formation of detrimental sulfur-containing salt phases in the melter. This study explored the effects of different compositions and additives on sulfur solubility. It was found that the addition of sulfur resulted in the formation of crystalline Cr2O3 and a separate salt phase called Na2(S,Cr)O4.
JOURNAL OF NON-CRYSTALLINE SOLIDS
(2022)
Article
Materials Science, Ceramics
Xinyi Xu, Rajan Saini, Enver Koray Akdogan, John Stuart McCloy, Ashutosh Goel
Summary: In this study, the impact of glass network formers, such as SiO2, B2O3, and Al2O3, on the corrosion of Monofrax K-3 refractory in a model nuclear waste glass composition has been investigated. Corrosion tests were conducted at 1150 degrees C for 5 days, revealing that Al2O3 and SiO2 tend to reduce the corrosion of the refractory, with Al2O3 having a significant effect. A corroded region at the melt-refractory interface was observed. The corrosion is primarily caused by the infiltration of the melt into the refractory through capillary effect, leading to dissolution of Al, Mg, and Fe components into the melt. A Cr-rich layer remains on the glass contact surface of the corroded K-3 refractory.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2023)
Article
Chemistry, Multidisciplinary
Hannah Smith, Luke T. Townsend, Ritesh Mohun, Theo Cordara, Martin C. Stennett, J. Frederick W. Mosselmans, Kristina Kvashnina, Claire L. Corkhill
Summary: This study investigates the fundamental chemistry of Cr-doped UO2 fuels and provides direct evidence of the chemistry of Cr2(3+)O3-doped U(4+)O2 using advanced analytical methods. The study shows that Cr2+ can directly substitute for U4+, accompanied by U5+ and oxygen vacancy charge compensation, explaining the substantial discrepancies in previous literature.
COMMUNICATIONS CHEMISTRY
(2022)
Article
Engineering, Chemical
Anjali Yadav, Saehwa Chong, Brian J. Riley, John S. McCloy, Ashutosh Goel
Summary: The article presents the complete process of I2(g) capture using Ag-exchanged faujasite (AgX) and Ag-exchanged mordenite (AgZ) zeolite sorbents, the recovery of Ag for recyclability of iodine capture, and the immobilization of iodide into iodosodalite waste form.
INDUSTRIAL & ENGINEERING CHEMISTRY RESEARCH
(2023)
Article
Materials Science, Multidisciplinary
John S. McCloy, Nicholas Stone-Weiss, David L. Bollinger
Summary: Caustic scrubbers (CS) are used to capture radioiodine in nuclear fuel reprocessing plants by reacting with dissolved anions and forming aluminosilicate powders. The CS aluminosilicates were characterized using Na-23 and Al-27 magic angle spinning nuclear magnetic resonance (NMR) to understand their crystalline and amorphous structures. The NMR results revealed the presence of various chemical environments in the mixed sodalite assemblage.
Article
Materials Science, Ceramics
Merve Kuman, Laura J. Gardner, Lewis R. Blackburn, Martin C. Stennett, Neil C. Hyatt, Claire L. Corkhill
Summary: In this study, a ceramic wasteform with dual-substituted zirconolite composition was successfully fabricated by hot isostatic pressing. The optimal milling parameters for the zirconolite phase synthesis were determined, leading to improved microstructure properties and higher yield.
CERAMICS-SWITZERLAND
(2023)
Article
Materials Science, Ceramics
Chenxu Wang, Pedaballi Sireesha, Jing Shang, John S. McCloy, Jin Liu, Wei -Hong Zhong
Summary: This study presents a green synthesis method to fabricate stable porous Fe2O3 as an anode material for Li-ion batteries. The synthesized material effectively accommodates volume change, reduces pulverization, and alleviates agglomeration, leading to a high capacity.
CERAMICS INTERNATIONAL
(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)