Article
Materials Science, Ceramics
Clifton H. Bumgardner, Frederick M. Heim, David C. Roache, Alex Jarama, Morgan C. Price, Christian P. Deck, Xiaodong Li
Summary: Evaluation of SiC/SiC CMCs in tension and bending under different loading conditions reveals insights into crack initiation, stress redistribution mechanisms, and microstructural influences. The study reaffirms the current state of these composites for energy applications and provides valuable information for further improvements in SiC/SiC and other CMCs.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2021)
Article
Materials Science, Multidisciplinary
Gyanender Singh, Brian D. Wirth
Summary: This study analyzes the bending behavior and stress development in SiC cladding, as well as the effects of spacer grids. The results indicate that spacer grids have minimal impact on cladding stresses, while the extent of circumferential power variation can significantly increase spacer grid stresses.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Energy & Fuels
Jizhen Zhu, Yueying Liang, Sixu Wang, Liang Yu, Dezhi Zhou, Yong Qian, Xingcai Lu
Summary: This study investigates the autoignition characteristics of dual-fuel (DF) combustion under marine engine-relevant conditions. The research finds that methanol has a greater impact on autoignition delay time (IDT) compared to methane, and exhibits ignition-promoting behavior at high temperatures. Methane/diesel DF engines are more prone to cycle-to-cycle variations, while methanol/diesel DF engines have larger cycle variations. The mixture fraction and mixing time play important roles in controlling the ignition. Additionally, the OH radicals and HO2 have significant effects on the reactivity, while the CH3OH + OH <=> CH2OH + H2O reaction shows the highest ignition-inhibition. CH3OH + HO2 <=> CH2OH + H2O2 has a promoting effect on IDTs at high temperatures, leading to IDT reduction.
Article
Nuclear Science & Technology
Fumihisa Nagase
Summary: The fracture threshold of the fuel decreases if the oxidized Zr alloy cladding is strongly constrained by the spacer grid during quenching in a loss-of-coolant accident. The constraint force of the Zircaloy grid gradually decreased with temperature, while the Inconel grid showed partial recovery of the constraint force during cooling.
ANNALS OF NUCLEAR ENERGY
(2022)
Article
Materials Science, Ceramics
Haitang Yang, Shenwei Xu, Daxu Zhang, Longbiao Li, Xiaozhong Huang
Summary: This study analyzed the tensile damage and fracture behavior of various SiC fiber bundles and composites, establishing relationships between load-displacement curves, stress-strain curves, and micro damage mechanisms. Predictions were made for the performance changes of the composites at different damage stages.
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
(2021)
Article
Materials Science, Ceramics
Justine Delage, Eduardo Saiz, Nasrin Al Nasiri
Summary: Ceramic matrix composites have excellent thermo-mechanical properties but lack standardized methods for characterizing fracture toughness. This study investigates the fracture behavior of silicon carbide materials reinforced by SiC fibers, identifying the toughening mechanisms and evaluating the fracture parameters.
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
(2022)
Article
Thermodynamics
G. Y. Su, T. A. Moreira, D. Lee, A. Jena, G. Wang, A. Byers, B. Phillips, Z. Karoutas, M. Anderson, M. Bucci
Summary: In this study, we experimentally evaluated the thermal-hydraulic performance of chromium-coated zircaloy, a promising material for accident tolerant fuel (ATF) cladding. The wettability and critical heat flux (CHF) limits of the chromium-coated and conventional zircaloy surfaces were investigated. The results showed that the wettability and steady-state CHF limits were similar for both surfaces, with the chromium-coated surface preventing the formation of brittle zirconium oxide. The transient CHF was found to be independent of surface finish for short time periods.
APPLIED THERMAL ENGINEERING
(2022)
Article
Energy & Fuels
Shengyu Liu, Rong Liu, Chengjie Qiu, Wenzhong Zhou
Summary: This study investigated the performance of thorium-based fuel with Cr-coated SiC/SiC composite cladding using the finite element multiphysics modeling method. The results showed that thorium-based fuels altered the fuel centerline temperature under different conditions compared to UO2 fuel, and the Cr-coated SiC/SiC composite cladding exhibited better mechanical performance.
FRONTIERS IN ENERGY RESEARCH
(2021)
Article
Cell Biology
Tim Hammersen, Justyna Buchert, Severin Zietzschmann, Solvig Diederichs, Wiltrud Richter
Summary: Increasing extracellular calcium levels can enhance cartilage neogenesis from human articular chondrocytes and bone marrow-derived mesenchymal stromal cells, but the effect is opposite for the two cell types.
Article
Energy & Fuels
Juan Daniel Martinez, Alberto Veses, Maria Soledad Callen, Jose Manuel Lopez, Tomas Garcia, Ramon Murillo
Summary: This work presents the fractionation of tire pyrolysis oil (TPO) in a continuous operational mode under industrially relevant conditions. By assessing different process parameters, the optimal conditions for producing light and heavy fractions with high recovery efficiency were determined.
Article
Materials Science, Ceramics
L. Gale, S. Harris, S. Pattison, J. Baker, J. Fowler
Summary: SiC/SiC ceramic matrix composites are being developed for aero-engines to replace nickel superalloy components. Sub-element testing is crucial for understanding the behavior of these materials. This study focused on high temperature C-shape sub-element testing and found that specimens were failing once they reached a critical radial stress level, with radial cracks initiating before circumferential cracks during both monotonic and fatigue tests.
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
(2021)
Article
Energy & Fuels
Yanzhi Zhang, Leilei Xu, Yizi Zhu, Shijie Xu, Xue-Song Bai
Summary: This paper presents a CFD modeling study on the fuel/air mixing characteristics of liquid ammonia under direct injection engine-relevant conditions. The study investigates the suitability of widely used Lagrange particle tracking (LPT) spray models for ammonia spray and proposes improvements for better prediction under flash boiling conditions. The research findings highlight the importance of considering the flash boiling model and spray included angle in accurately reproducing the characteristics of liquid ammonia spray and suggest the need for a more accurate flash boiling model that considers the thermal breakup effect.
Article
Nuclear Science & Technology
Hongyang Wei, Jing Zhang, Xiaobin Jian, Yongdong Zhang, Lei Li, Shurong Ding, Qisen Ren
Summary: In this study, the effects of TRISO particle volume fraction, particle distribution pattern, and irradiation conditions on the thermal-mechanical behavior in FCM fuel pellets were investigated using the self-developed code TMAIMF. The results show that increasing the particle volume fraction leads to an increase in central temperature and a decrease in radial size increment, while the maximum tensile stresses of each coating layer of the TRISO particles vary slightly. The distribution pattern of the particles has a weak influence on temperature, deformation, and maximum tensile stress. The integrity of FCM pellets can be maintained under high fission rate conditions and extended burnup levels. The finite element models with axial displacement constrained are representative and yield more conservative analysis results compared to the free-end models. The numerical simulation results demonstrate the flexibility of optimizing TRISO-particle-based fuel pellets to meet the demands of economy and safety.
NUCLEAR MATERIALS AND ENERGY
(2023)
Article
Thermodynamics
Jiabo Zhang, Minh B. Luong, Hong G. Im
Summary: This study numerically investigates the detonation development of carbon-free fuels, namely ammonia and hydrogen (NH3 and H2), using one-dimensional simulations. The detonation peninsulas are quantitatively identified by two non-dimensional parameters, xi and epsilon. Increasing the H2 blending ratio up to 80% results in a unique horn-shaped detonation peninsula, and a correction factor, beta, is proposed to resolve the discrepancy of the xi u,l limits.
COMBUSTION AND FLAME
(2023)
Article
Biotechnology & Applied Microbiology
Sun-Il Kim, Jin-Woo Kim, Ki-Tae Kim, Chang-Ho Kang
Summary: The study confirmed the protective effect of low molecular weight collagen-peptide on microbial stability damaged by freezing, and its ability to increase bacterial survivability in the gastrointestinal tract. Low molecular weight collagen-peptide, as a novel protective agent, shows potential in improving the stability of various probiotics.
FERMENTATION-BASEL
(2021)
Article
Materials Science, Ceramics
Huaxin Li, Takaaki Koyanagi, Caen Ang, Yutai Katoh
Summary: The study successfully demonstrated the joining of SiC materials at relatively low temperature through the electric current-assisted joining (ECAJ) method. Enhancing the current passage achieved the joining of low-resistivity grade, nitrogen doped beta-SiC; rapid crystal growth of textured SiC was found at the interface when joining at higher temperatures.
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
(2021)
Article
Materials Science, Multidisciplinary
Takaaki Koyanagi, Kurt Terrani, Shay Harrison, Jian Liu, Yutai Katoh
Summary: This paper explores the application of additive manufacturing technology to produce nuclear-grade silicon carbide, analyzing the impact of different microstructures on the behavior of SiC in nuclear environments, and discussing the latest AM technologies for manufacturing relatively pure SiC.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
D. J. Sprouster, J. R. Trelewicz, L. L. Snead, X. Hu, D. Morrall, T. Koyanagi, C. M. Parish, L. Tan, Y. Katoh, B. D. Wirth
Summary: This paper discusses the importance of state-of-the-art synchrotron-based x-ray characterization methods in fusion material research, with examples highlighting the quantitative characterization of microstructural evolution and radiation response in advanced materials. The opportunities in leveraging synchrotron techniques to address materials science challenges and support modeling efforts are showcased through specific case studies.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Masafumi Akiyoshi, Lauren M. Garrison, Josina W. Geringer, Hsin Wang, Akira Hasegawa, Shuhei Nogami, Yutai Katoh
Summary: The Japan-US PHENIX project irradiated tungsten materials in the HFIR reactor using Gd shielding to absorb thermal neutrons. The thermal diffusivity of irradiated specimens was compared at different temperatures and annealing conditions, showing limited contribution of crystalline defects to the degradation of thermal diffusivity. The results indicated that the thermal diffusivity of irradiated specimens approached that of unirradiated specimens at elevated temperatures.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Peter J. Doyle, Caen Ang, Lance Snead, Yutai Katoh, Kurt Terrani, Stephen S. Raiman
Summary: Four different commercial coatings were deposited on high resistivity SiC for corrosion mitigation and fission gas hermeticity testing. The Cr/CrN coating quickly spalled, while the CrN coating preferentially spalled in oxygenated conditions. TiN coatings fully oxidized and spalled, but all coatings were chemically stable in hydrogen. Localized spallation was identified as a common issue across all coatings. Future improvements are recommended for better protection.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
B. K. Kim, L. Tan, H. Sakasegawa, C. M. Parish, W. Zhong, H. Tanigawa, Y. Katoh
Summary: The study revealed that doping with Ni-58 resulted in greater strengthening contributions from loops and cavities, leading to higher hardening and lower ductility compared to Ni-60 doping in reduced-activation ferritic-martensitic steels under helium irradiation.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Nanoscience & Nanotechnology
Takaaki Koyanagi, David J. Sprouster, Lance L. Snead, Yutai Katoh
Summary: High-energy x-ray diffraction was used to investigate the irradiation-induced creep behavior of silicon carbide (SiC), revealing that stress-induced stacking disorder plays a key role in creep mechanism in neutron-irradiated SiC.
SCRIPTA MATERIALIA
(2021)
Article
Materials Science, Multidisciplinary
Chinthaka Silva, Miao Song, Mi Wang, Kiel Holliday, Keith Leonard, Gary Was, Jeremy Busby
Summary: Solution annealing temperature has an impact on the irradiation performance of alloy 718, with samples processed at high temperatures showing better performance under irradiation.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
John Echols, Lauren Garrison, Chinthaka Silva, Elizabeth Lindquist
Summary: The study shows that post-weld heat treatments of Zry-4 tungsten inert gas (TIG) welds between 450-900 degrees Celsius can improve ductility, with the treatment at 800 degrees Celsius for 1 hour producing the most ductile material. Both the PWHT time and temperature can increase total elongation, except in extreme cases where temperatures exceed 800 degrees Celsius or hold times are greater than 18 hours.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Chemistry, Analytical
Bradley C. Childs, Aiden A. Martin, Emily E. Moore, Tae Wook Heo, Aurelien Perron, Cherie Schaeffer-Cuellar, Andrew J. Swift, Chinthaka M. Silva, Kiel S. Holliday, Jason R. Jeffries
Summary: The study reports the decomposition pathways of uranium triiodide and ammonium uranium fluoride during laser-induced heating, supported by a computational thermodynamics technique. Results show rapid decomposition of material via laser heating, forming desired products for nuclear fuel cycle research.
JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY
(2021)
Article
Nanoscience & Nanotechnology
Chinthaka M. Silva, Keith J. Leonard, Lauren M. Garrison, Chris D. Bryan
Summary: The study investigated the microstructural and mechanical properties of a lean duplex stainless steel material (2304-grade) under irradiation conditions, showing radiation hardening and decreased total elongation. Fracture surfaces of irradiated samples exhibited nonuniform quasi-cleavage and shearing, indicative of radiation-induced embrittlement. Furthermore, elemental segregation was identified in the post-irradiated base metal.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
(2021)
Article
Chemistry, Physical
Chinthaka M. Silva, Thomas M. Rosseel, Kiel S. Holliday
Summary: The crystallography and crystal structure of calcite and dolomite in nuclear power plant concrete were affected by neutron irradiation. The irradiation caused an expansion of the unit cells, with dolomite showing a continuous increase in lattice parameters. Radiation-induced disordering of the crystal structure was observed in both materials, while a healing effect was mainly observed in calcite. The Mg sites were more sensitive to neutron irradiation compared to the Ca sites.
JOURNAL OF PHYSICAL CHEMISTRY C
(2022)
Article
Chemistry, Inorganic & Nuclear
Maryline G. Ferrier, Bradley C. Childs, Chinthaka M. Silva, Michelle M. Greenough, Emily E. Moore, Andrew J. Swift, Silvina A. Di Pietro, Aiden A. Martin, Jason R. Jeffries, Kiel S. Holliday
Summary: The thermal decomposition of UI4(1,4-dioxane)(2) was studied under laser irradiation, and it was found that the reaction produced UO2, U(C1-xOx)(y), UC2-zOz, and UC instead of pure U metal. The results suggest the potential of co-developing uranium precursors with specific irradiation procedures to find new pathways for producing uranium carbide.
INORGANIC CHEMISTRY
(2022)
Article
Chemistry, Inorganic & Nuclear
Chinthaka M. Silva, Kyle J. Kondrat, Kiel S. Holliday, Scott J. McCormack
Summary: This study evaluated two pathways for synthesizing HfN and HfC: direct nitridation and carbothermic reduction/nitridation. The experimental results showed that the HfC1-yN y phase formed at high temperatures and had lower lattice strain and larger crystallite sizes, suggesting that HfC1-yN y phase is preferred over HfN at those temperatures.
INORGANIC CHEMISTRY
(2023)
Article
Materials Science, Multidisciplinary
Cuncai Fan, Congyi Li, Chad M. Parish, Yutai Katoh, Xunxiang Hu
Summary: Tungsten has been studied as a potential plasma facing material for future fusion reactors, with research focusing on the effects of helium ion-beam irradiation on different crystallographic orientations. The results show that radiation damage, helium thermal desorption, and surface/subsurface evolution are all strongly influenced by crystallographic orientation in tungsten. The findings provide new insights into the behavior of helium in tungsten materials.
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)