Article
Materials Science, Multidisciplinary
Rebecca Dowek, Celine Cagna, Jean Noirot, Isabelle Zacharie-Aubrun, Thierry Blay, Karine Hanifi, Philippe Bienvenu, Ingrid Roure, Martiane Cabie, Myriam Dumont
Summary: Two methods were developed to evaluate the gas density in micrometric or quasi-micrometric bubbles formed in oxide nuclear fuels during high burn-up or high temperature periods, providing useful experimental information for understanding fuel behavior, code progress and validation. The methods involve using electron probe micro analyser, secondary ion mass spectrometry and focused ion beam scanning electron microscope.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
J. L. Wormald, A. I. Hawari
Summary: In fission-based nuclear reactors, the interaction between fission fragments and electronic excitations leads to thermalization and the formation of high temperature thermal spikes. This promotes atomic mobility and lattice defects formation. A multigroup model for electron energy transport is developed to simulate fission energy deposition in nuclear fuel. The results show reasonable agreement with experimental trends and provide insights into fission effects.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Materials Science, Multidisciplinary
M. Gerardin, E. Gilabert, D. Horlait, M-f. Barthed, G. Carlot
Summary: The production and release of fission gases have a significant impact on uranium dioxide fuel performance. A better understanding of fission gas behavior in uranium dioxide is needed to predict fuel properties in a nuclear reactor. Experiments with low-dose implantation of xenon or krypton in UO2 samples were conducted to avoid trapping by irradiation defects and/or gas clusters. The release rates of xenon and krypton were studied, and the results showed excellent agreement with previous literature on xenon diffusion in irradiated UO2.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Astronomy & Astrophysics
K. Mahata, C. Schmitt, Shilpi Gupta, A. Shrivastava, G. Scamps, K-H Schmidt
Summary: A regular pattern is observed in the low-energy asymmetric fission of neutron-deficient nuclei around lead, with the leading role attributed to the light-fragment nuclear charge. This finding challenges previous theoretical interpretations and highlights the importance of proton configurations driven by quadrupole-octupole correlations. The survey of a wider area of the nuclear chart points to a lack of quantitative understanding of the competition between macroscopic and microscopic forces. Furthermore, a connection between old and new islands of asymmetric fission indicates a potential pathway towards a unified theory of fission.
Review
Materials Science, Multidisciplinary
Serge Maillard, David Andersson, Michel Freyss, Fabien Bruneval
Summary: This paper reviews the role of atomistic techniques in building defect models in crystals and their effectiveness in reproducing important experimental data. Using non-stoichiometric uranium dioxide as an example, eleven point-defect models from the literature are compared and significant differences in defect formation energies and entropies are found. Atomistic-based models face difficulties in predicting the oxygen potential and OM ratio, which may arise from erroneous calculations of the oxygen molecule energy and the energy of oxygen incorporation in UO2, as well as a poor evaluation of the electron-hole formation Gibbs energy.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Materials Science, Multidisciplinary
C. O. T. Galvin, M. J. D. Rushton, M. W. D. Cooper, D. A. Andersson, P. A. Burr, R. W. Grimes
Summary: This study used molecular dynamics and Monte Carlo simulations to predict the lowest energy shapes for voids and bubbles in UO2. It was found that low energy faceted voids are slightly more energetically favourable than spherical voids, and as Xe is added and bubble pressure increases, the faceted morphology becomes even more favourable than the spherical shape.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Energy & Fuels
Prosper Nekekpemi, Fathi Boukadi, Olatunji Olayiwola
Summary: A new empirical correlation model has been developed in this study to predict the minimum miscibility pressure (MMP) of flue gas in previously waterflooded light oil reservoirs. The newly built model is more accurate and delivers better predictions compared to existing correlations.
JOURNAL OF PETROLEUM EXPLORATION AND PRODUCTION TECHNOLOGY
(2022)
Article
Chemistry, Inorganic & Nuclear
Yun-Nan Gong, Jin-Wang Liu, Jian-Hua Mei, Xue-Lian Lin, Ji-Hua Deng, Xiaokang Li, Di-Chang Zhong, Tong-Bu Lu
Summary: Incorporating chromophores into metal-organic frameworks can lead to the construction of stable and efficient catalysts for CO2 conversion, as shown by the successful synthesis of the porous Nd(III) MOF (Nd-TTCA). This work provides a new strategy for designing artificial crystalline catalysts for efficient CO2 conversion, with Nd-TTCA demonstrating significant improvements in both photocatalytic and catalytic activities compared to the organic ligand H(3)TTCA.
INORGANIC CHEMISTRY
(2021)
Article
Materials Science, Multidisciplinary
Benjamin Beeler, Michael W. D. Cooper, Zhi-Gang Mei, Daniel Schwen, Yongfeng Zhang
Summary: Monolithic U-Mo alloy fuel design has been chosen for conversion of U.S. High-Performance Research Reactors, with a focus on the significant swelling during operation at high fission densities. Accurate prediction of fuel evolution under irradiation requires incorporation of correct thermodynamic and kinetic properties into modeling codes, particularly accurate representation of diffusion for determining fission gas swelling rate and local microstructural evolution. This work presents molecular dynamics simulations of radiation driven diffusion in U-Mo nuclear fuels to determine diffusion coefficients applicable under irradiation.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Physics, Multidisciplinary
Sonia M. Reda, Emad Khalil, Dalia Anwar, Ahmed Youssef
Summary: The present work aims to investigate the effects of adding uranium dioxide (UO2) to deuterium fuel in fusion-fission hybrid reactions. It was found that applying a reflector surface significantly increased the neutron flux in D-D fusion reactions, and adding 1.0 gm of UO2 enhanced neutron flux and generated power.
Article
Materials Science, Multidisciplinary
Christian M. Petrie, Kory D. Linton, Gokul Vasudevamurthy, Danny Schappel, Rachel L. Seibert, David Carpenter, Andrew T. Nelson, Kurt A. Terrani
Summary: This work summarizes the initial testing of TCR fuel materials, including loose UCN TRISO particles and integral fuel compacts, to evaluate fission gas retention. Fission gasses were fully retained in all loose particle tests and in integral compacts irradiated at low surface temperatures. However, high temperature testing showed fission gas release and complete fracture of some compacts, but later high temperature testing did not show fission gas release.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Review
Materials Science, Multidisciplinary
Liu Shuai, Guo Zixuan, Xin Yong, Wang Haoyu, Liu Shichao, Bao Hongwei, Ma Fei
Summary: This paper systematically discusses the types of doped elements and their influence on the performance of uranium dioxide fuel pellets, as well as the relationship between the microstructure and performance of doped fuel. It also points out the existing problems and development trends for doped uranium dioxide fuel, providing valuable references for enhancing the safety performance of fuel pellets.
RARE METAL MATERIALS AND ENGINEERING
(2021)
Article
Chemistry, Multidisciplinary
Jingyu Guo, Songbai Cheng, Kai Wang, Wenzhong Zhou
Summary: Fission gas behavior is crucial for accident assessment and evaluating fuel rod performance. This study presents an extended model for predicting fission gas release in light water reactors. The model is validated using input parameters from other models and experiments. The results show that diffusion coefficients, temperatures, grain sizes, and linear heat generation rates all have an influence on the fission gas release fraction.
APPLIED SCIENCES-BASEL
(2023)
Article
Physics, Nuclear
C. Kokila, M. Balasubramaniam
Summary: This study investigates the pre-existence probability of ternary breakup for Cf isotopes, examining various third fragments and clusters. Deformation affects the most probable distribution, with increased yield when main fission fragment distance is reduced. Different clusters lead to different yield distributions, with heavier clusters favoring specific fragmentation patterns in agreement with experimental predictions.
JOURNAL OF PHYSICS G-NUCLEAR AND PARTICLE PHYSICS
(2021)
Article
Materials Science, Multidisciplinary
Randall D. Scheele, Brady D. Hanson, Andrew M. Casella
Summary: The study found that the oxidation of UO2 proceeds through at least three steps, increasing Gd content does not delay the oxidation onset temperature to U3O7/U4O9 but slows down the oxidation process and delays the onset of the second oxidation to U3O8. The kinetic mechanisms for the two oxidations depended on Gd content, with the first oxidation proceeding via often overlapping Phase Boundary, Nucleation & Growth, and Diffusion mechanisms and the second oxidation proceeding via often overlapping Nucleation & Growth, Phase Boundary, 1st and 2nd Order Chemical, and Diffusion.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
R. M. Boothby, J. M. Hyde, H. Swan, D. Parfitt, K. Wilford, P. Lindner
JOURNAL OF NUCLEAR MATERIALS
(2015)
Article
Materials Science, Multidisciplinary
Marjorie Bertolus, Michel Freyss, Boris Dorado, Guillaume Martin, Kiet Hoang, Serge Maillard, Richard Skorek, Philippe Garcia, Carole Valot, Alain Chartier, Laurent Van Brutzel, Paul Fossati, Robin W. Grimes, David C. Parfitt, Clare L. Bishop, Samuel T. Murphy, Michael J. D. Rushton, Dragos Staicu, Eugen Yakub, Sergii Nichenko, Matthias Krack, Fabien Devynck, Raoul Ngayam-Happy, Kevin Govers, Chaitanya S. Deo, Rakesh K. Behera
JOURNAL OF NUCLEAR MATERIALS
(2015)
Article
Materials Science, Multidisciplinary
P. D. Styman, J. M. Hyde, D. Parfitt, K. Wilford, M. G. Burke, C. A. English, P. Efsing
JOURNAL OF NUCLEAR MATERIALS
(2015)
Article
Microscopy
P. D. Styman, J. M. Hyde, K. Wilford, D. Parfitt, N. Riddle, G. D. W. Smith
Article
Chemistry, Multidisciplinary
Alexander Chroneos, Bilge Yildiz, Albert Tarancon, David Parfitt, John A. Kilner
ENERGY & ENVIRONMENTAL SCIENCE
(2011)
Article
Nuclear Science & Technology
H. Lu, S. T. Murphy, M. J. D. Rushton, D. C. Parfitt, R. W. Grimes
FUSION ENGINEERING AND DESIGN
(2012)
Article
Chemistry, Physical
David Parfitt, Alexander Chroneos, Albert Tarancon, John A. Kilner
JOURNAL OF MATERIALS CHEMISTRY
(2011)
Article
Materials Science, Multidisciplinary
S. C. Middleburgh, D. C. Parfitt, R. W. Grimes, B. Dorado, M. Bertolus, P. R. Blair, L. Hallstadius, K. Backman
JOURNAL OF NUCLEAR MATERIALS
(2012)
Article
Materials Science, Multidisciplinary
K. Govers, C. L. Bishop, D. C. Parfitt, S. E. Lemehov, M. Verwerft, R. W. Grimes
JOURNAL OF NUCLEAR MATERIALS
(2012)
Article
Physics, Condensed Matter
David C. Parfitt, Clare L. Bishop, Mark R. Wenman, Robin W. Grimes
JOURNAL OF PHYSICS-CONDENSED MATTER
(2010)
Article
Materials Science, Ceramics
Simon C. Middleburgh, David C. Parfitt, Paul R. Blair, Robin W. Grimes
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2011)
Article
Physics, Applied
A. Chroneos, D. Parfitt, R. V. Vovk, I. L. Goulatis
MODERN PHYSICS LETTERS B
(2012)
Article
Chemistry, Physical
Akihiro Kushima, David Parfitt, Alexander Chroneos, Bilge Yildiz, John A. Kilner, Robin W. Grimes
PHYSICAL CHEMISTRY CHEMICAL PHYSICS
(2011)
Article
Materials Science, Multidisciplinary
P. V. Nerikar, D. C. Parfitt, L. A. Casillas Trujillo, D. A. Andersson, C. Unal, S. B. Sinnott, R. W. Grimes, B. P. Uberuaga, C. R. Stanek
Article
Chemistry, Physical
I. D. Seymour, A. Tarancon, A. Chroneos, D. Parfitt, J. A. Kilner, R. W. Grimes
SOLID STATE IONICS
(2012)
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)