Article
Nuclear Science & Technology
Abdulsamad Asuku, Yakubu Viva Ibrahim, Sunday Adesunloye Jonah, Umar Sadiq, John Simon
Summary: This study models the Nigerian Research Reactor-1 (NIRR-1) and calculates the core neutronic parameters using SCALE 6.2.3 computational tools. The results show that the candidate LEU fuels are suitable for converting MNSRs from HEU to LEU.
PROGRESS IN NUCLEAR ENERGY
(2022)
Article
Materials Science, Multidisciplinary
Jiatu Liu, Patrick A. Burr, Joshua T. White, Vanessa K. Peterson, Pranesh Dayal, Christopher Baldwin, Deborah Wakeham, Daniel J. Gregg, Elizabeth S. Sooby, Edward G. Obbard
Summary: U3Si2 nuclear fuel corrodes in deuterated steam, and hydrogen adsorbs at specific sites with temperature dependence. The temperature range of corrosion reactions and preference for specific sites have been determined.
Article
Materials Science, Multidisciplinary
B. Ye, Y. Miao, J. Shi, D. Salvato, K. Mo, L. Jamison, A. Bergeron, G. L. Hofman, A. Leenaers, A. Oaks, A. M. Yacout, S. Van den Berghe, W. Petry, Y. S. Kim
Summary: The study investigated the temperature dependence of interdiffusion in bilayer Al-UMo samples through ion irradiation experiments and numerical simulations. The results showed a clear transition point at 175 degrees C, which is crucial for understanding the interdiffusion process in U-Mo/Al dispersion fuels. An activation energy of 0.77 +/- 0.16 eV was determined from the interdiffusion quantity vs. irradiation temperature curve. Simulation with the Dispersion Analysis Research Tool (DART) demonstrated good agreement between calculated and measured data, capturing the temperature effect on in-pile Al-UMo interdiffusion. The fitted activation energy from in-pile data (0.70 eV) accorded with the ion irradiation results.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Yong-Sheng Li, Hui-Yu Wang, Jing Chen, Shuai-Ge Yang, Peng Sang, Hong-Li Long
Summary: The study found that under different temperature gradients, the interdiffusion interface of Ni-Al-Cr/Ni-Al-Cr layered alloys forms a precipitate-free zone, and elements exhibit different diffusion behaviors depending on the Cr or Al concentrations.
Article
Chemistry, Physical
Sruthi Mohan, Renjith Ramachandran, C. David, G. Amarendra
Summary: ODS ferritic steels containing Zr with and without Al addition were synthesized, showing homogeneous distribution of nanoprecipitates and nanometric grain sizes. Positron lifetime measurements indicated different trapping behaviors in dislocations and vacancy clusters in the two alloys.
JOURNAL OF ALLOYS AND COMPOUNDS
(2022)
Article
Chemistry, Physical
Sruthi Mohan, Renjith Ramachandran, C. David, G. Amarendra
Summary: The study shows that oxide dispersion strengthened ferritic steels containing Zr can delay defect production, possess excellent trapping capability, and have homogeneous distribution of nanometric grain sizes.
JOURNAL OF ALLOYS AND COMPOUNDS
(2022)
Article
Materials Science, Multidisciplinary
Y. T. Li, T. Li, W. Li, L. J. Fan, S. Y. Zhang, S. M. Jiang, J. Gong, C. Sun
Summary: Pt modified aluminide (Pt-Al) coatings were prepared on third- and fourth-generation single crystal superalloys by electroplating Pt and successive aluminization. The isothermal oxidation behaviors of both coatings were investigated at 1100 celcius for 350 h. The Pt-Al coating on the fourth-generation single crystal superalloy demonstrated superior oxidation resistance. Ru diffusion into the Pt-Al coating during isothermal oxidation increased spallation resistance of oxide scale. The effects of Ru on the anti-spallation property of oxide scale and the interdiffusion between coating and substrate were discussed. The diffusion process of Ru was investigated.
Article
Chemistry, Physical
A. Kostka, D. Naujoks, T. Oellers, S. Salomon, C. Somsen, E. oeztuerk, A. Savan, A. Ludwig, G. Eggeler
Summary: In this study, the process of layer growth in the Ni-Al system was investigated through experiments and observations. The results showed that a polycrystalline aluminide layer formed in the early stage of the solid-state reaction, followed by preferential grain growth in the later stage. It was also found that two different aluminide phases formed simultaneously. In-situ TEM study revealed the time dependence of layer growth rate. The findings provide insights into the growth mechanism of reaction layers and suggest areas for further research.
JOURNAL OF ALLOYS AND COMPOUNDS
(2022)
Article
Materials Science, Multidisciplinary
R. Beygi, R. Carbas, A. Queiros, E. A. S. Marques, R. Shi, L. F. M. da Silva
Summary: The study found that different alloying elements in steel have different effects on the formation of IMCs. The IMC layer in SS/Al joints is thinner than that in CS/Al joints, partly due to the alloying elements in stainless steel such as Ni and Cr hindering the growth rate of IMCs. At high rotation speed, liquation occurred in SS/Al joints, reducing the nucleation rate of IMCs.
METALS AND MATERIALS INTERNATIONAL
(2022)
Article
Chemistry, Physical
Dasom Kim, Kyungju Kim, Hansang Kwon
Summary: This study systematically investigated the interdiffusion mechanism at Al/Cu interfaces in relation to process temperature, finding that the thickness of the interdiffusion layer drastically increased above 400 degrees C, forming intermetallic compounds like CuAl2 and Cu9Al4. The Al-50vol.%Cu composite sintered at 380 degrees C exhibited high Vickers hardness and thermal conductivity, suggesting that a material with good mechanical strength and heat conductance can be prepared by solid-state sintering at a low temperature.
Article
Materials Science, Multidisciplinary
Huan Liu, Luca Messina, Antoine Claisse, Simon C. Middleburgh, Thomas Schuler, Par Olsson
Summary: Uranium silicide U3Si2 is considered as an advanced nuclear fuel for commercial light water reactors, and studies have shown that the diffusion rate of Neodymium in this concept fuel is faster than in conventional oxide fuels. Therefore, Neodymium can be considered as a burnup indicator in U3Si2.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Xue-Ting Wu, Cheng-Hui Xia, Xiao-Gang Lu
Summary: In this study, a 2D inverse scheme was developed to efficiently deduce the composition-dependent interdiffusivity matrices of a Co-Al-Ta diffusion triple in the fcc phase. The interdiffusivities deduced from the 2D inverse scheme showed expected agreements with those extracted using the traditional Sauer-Freise method. Additionally, visual presentations of the interdiffusion fluxes and the shift of the Kirkendall plane in the 2D diffusion zone were provided. The resulting 2D mapping revealed new appearances of non-uniform but curved Kirkendall planes, which were well explained by the calculated diffusion variables.
METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE
(2023)
Article
Materials Science, Multidisciplinary
Xiaoyu Sun, Pimin Zhang, Johan Moverare, Xin-Hai Li, Luqing Cui, Ru Lin Peng
Summary: The addition of Ta in MCrAlY coatings improves the oxidation resistance and reduces the depletion of γ' phase in the substrate. Thermodynamic simulations reveal the phase-transformation mechanism induced by initial interdiffusion and uncover the mechanism behind the improved resistance to γ' depletion by Ta addition.
MATERIALS & DESIGN
(2023)
Article
Materials Science, Multidisciplinary
M. W. D. Cooper, K. A. Gamble, L. Capolungo, C. Matthews, D. A. Andersson, B. Beeler, C. R. Stanek, K. Metzger
Summary: U3Si2, an advanced fuel candidate with high fissile density and thermal properties, has data gaps in thermophysical and thermomechanical properties. This study used DFT and MD simulations to predict point defect concentrations under irradiation, informing a creep model based on diffusional creep and dislocation creep, which compares well with experimental data and has been implemented in a fuel performance code. Demonstrations show negligible creep in U3Si2 due to its high thermal conductivity at low reactor temperatures.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Physics, Applied
Bangfei Zhou, Wenhao Lin, Ying Liu, Hao Cai, Tianxiang Zheng, Chunmei Liu, Yunbo Zhong
Summary: This study investigates atomic diffusion in liquid melts and finds that the thermoelectric magnetic convection can be suppressed or eliminated by increasing the magnetic flux density or using an insulated crucible. This allows for accurate measurement of the interdiffusion coefficient and provides a new perspective on studying alloy solidification under static magnetic fields.
JOURNAL OF APPLIED PHYSICS
(2022)
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)
