Article
Materials Science, Multidisciplinary
Sarah L'haridon Quaireau, Kimberly Colas, Benedicte Kapusta, Benedicte Verhaeghe, Marie Loyer-Prost, Gaelle Gutierrez, Dominique Gosset, Sylvie Delpech
Summary: In this study, the effects of ion irradiation on corrosion of aluminium alloys were investigated through experiments, with observed changes in the metal matrix and hydroxide film.
JOURNAL OF NUCLEAR MATERIALS
(2021)
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
Engineering, Electrical & Electronic
Haonan Feng, Xiaowen Liang, Xiaojuan Pu, Sheng Yang, Jie Feng, Ying Wei, Yutang Xiang, Jing Sun, Dan Zhang, Yudong Li, Qingkui Yu, Xuefeng Yu, Qi Guo
Summary: The static and dynamic characteristics of silicon carbide (SiC) MOSFETs exhibit differential degradation after irradiation, with threshold voltage shift and switch response degradation. The dependence of these two parameters on the bias is not the same. The accumulation of gate oxide traps in the localized region of trench gate MOS is the main reason for the special degradation of electrical parameters under drain bias. Considering both static and dynamic performances is important for evaluating radiation damage and radiation hardening of SiC MOSFETs under different biases.
IEEE TRANSACTIONS ON NUCLEAR SCIENCE
(2023)
Article
Materials Science, Multidisciplinary
Xiang Fu, Biao Wei, Jianbin Kang, Wangping Wang, Ge Tang, Qian Li, Feiliang Chen, Mo Li
Summary: This study reports the impact of fast neutron irradiation on the dark current and gain characteristics of Si-based and GaN-based APDs. The dark current of Si-based APDs increases with neutron fluence, while the gain decreases at high fluence. In contrast, the avalanche property of GaN-based APDs is almost unaffected. The optical absorption between the acceptor state and the conduction band in the p-type layer plays a crucial role in influencing the change of dark current and gain at high reverse bias voltage.
RESULTS IN PHYSICS
(2022)
Article
Engineering, Electrical & Electronic
R. L. Gao, X. Du, W. Y. Ma, B. Sun, J. L. Ruan, X. Ouyang, H. Li, L. Chen, L. Y. Liu, X. P. Ouyang
Summary: This study investigates the characteristics of 4H-SiC PIN diode detectors under harsh neutron irradiation environments. The results show that the detectors exhibit excellent neutron radiation tolerance and maintain relatively stable performance even after irradiation.
SENSORS AND ACTUATORS A-PHYSICAL
(2022)
Article
Materials Science, Multidisciplinary
Xinmei Yang, Huajian Liu, Xiaodong Wang, Min Liu, Jianqiang Wang, Xingtai Zhou, Yuan Qian
Summary: The role of helium ion irradiation in the corrosion of CVD-SiC in molten LiF-NaF-KF salt was studied, showing that it enhances the diffusion of silicon element. Additionally, helium ions also break down Si-C bonds to form defects, further increasing the corrosion of SiC.
Article
Materials Science, Multidisciplinary
Xiao Cui, Keyu Ji, Taiping Zhang, Bingjun Wang, Wei Sha, Zilong Dong, Yuanhong Shi, Chunsheng Jiang, Qilin Hua, Weiguo Hu
Summary: This paper investigates the influence of low-fluence neutron irradiation on the electrical properties of AlGaN/GaN HEMTs. The results show that the output performance of the irradiated samples changes similarly, with almost no changes or slight decreases near the knee voltage. As for the leakage current, samples irradiated with different fluences exhibit different characteristics. Simulations using Crosslight software further reveal that low-fluence neutron irradiation primarily affects the 2DEG mobility and surface states of the HEMTs.
ADVANCED MATERIALS TECHNOLOGIES
(2023)
Review
Polymer Science
Mansoureh Jamalzadeh, Margaret J. Sobkowicz
Summary: Ionizing radiation can modify the chemical structure and properties of polymer materials like PET through various reactions such as chain scission, crosslinking, and structural transformation. It can create new chemical bonds and different crystalline arrangements. By regulating the absorbed dosage, irradiation processing can provide customized optical, physical, and mechanical properties for PET in different applications.
POLYMER DEGRADATION AND STABILITY
(2022)
Article
Materials Science, Multidisciplinary
Arunkumar Seshadri, Bren Phillips, Koroush Shirvan
Summary: The study investigates the hydrothermal corrosion behavior of unirradiated and irradiated SiC, finding that surface roughness and irradiation damage accelerate dissolution. An analysis on CRUD deposition on SiC corrosion reveals that a stable CRUD layer significantly reduces SiC dissolution rates.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Biochemistry & Molecular Biology
Xiaoqing Lei, Jiangtao Yu, Yayun Hu, Junqing Bai, Shuo Feng, Yamei Ren
Summary: Electron beam and X-ray treatment have become increasingly important in the field of material modification. In this study, potato starch was irradiated with electron beam and X-ray at different doses, and it was found that both treatments increased the amylose content of starch. While the surface morphology of starch remained unchanged at lower doses, starch granules aggregated with increasing doses. Both treatments resulted in decreased crystallinity, viscosity, and swelling power, but increased solubility and stability properties. Electron beam had a lesser impact on the crystallinity of starch compared to X-ray, leading to improved thermal stability and freeze-thaw stability. X-ray irradiation at higher doses demonstrated outstanding anti-retrogradation properties compared to electron beam treatment. Overall, electron beam and X-ray irradiation show great potential in modifying starch with specific characteristics, thereby expanding their application in the starch industry.
INTERNATIONAL JOURNAL OF BIOLOGICAL MACROMOLECULES
(2023)
Article
Materials Science, Multidisciplinary
Hirotatsu Kishimoto, Joon-Soo Park, Naofumi Nakazato, Akira Kohyama
Summary: Claddings of silicon carbide (SiC)-based composites are crucial for enhancing nuclear safety, but joint parts are prone to damage during neutron irradiation experiments, highlighting the need for further development of joining and coating technologies.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Jing Yang, Ce Zheng, Shanshan Xu, Chong Wei, Cheng Zhang, Yichun Bi, Xiaoqiang Li
Summary: In this study, the radiation-induced microstructure evolution of M55J and T300 carbon fibers in C/SiC composites was investigated. Both carbon fibers exhibited axial shrinkage after irradiation, with M55J fibers showing slightly lower shrinkage compared to T300 fibers. Detailed microstructure characterization revealed disruptions in the graphite structure of both carbon fibers due to ion irradiation. The ordering degree of T300 fibers increased at low doses and decreased at higher doses, and possible mechanisms for the healing process in T300 fibers were discussed.
MATERIALS CHARACTERIZATION
(2023)
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
Physics, Multidisciplinary
R. Rayaprolu, S. Moeller, I Spahn, D. Hoschen, Ch Linsmeier
Summary: In a pilot experiment, 16 MeV protons were used to irradiate 300 μm thick W samples to a damage dose of 0.006 dpa under low and high temperature conditions. The electronic loss in the sample was observed to be 1.5 MW·m(-2) in the pre-Bragg region. Post high-temperature irradiation, recrystallization of the W sample was observed, leading to a surface softening of 0.6 GPa.
Article
Materials Science, Multidisciplinary
Xiang Fu, Jianbin Kang, Ge Tang, Feiliang Chen, Qian Li, Mo Li, Biao Wei
Summary: AlGaN-based deep ultraviolet (DUV) light emitting diodes (LEDs) exhibit significant enhancement of output power under neutron irradiation, but performance degradation occurs as neutron fluence increases. The study identifies two competitive mechanisms of neutron radiation effect on DUV LEDs, where increased carrier efficiency in irradiated multi-quantum wells contributes to output power enhancement, while neutron irradiation-induced nitrogen vacancies in the electron blocking layer lead to current leakage and device degradation. These findings not only enrich the degradation mechanism of neutron-irradiated DUV LEDs, but also offer new insights to improve their luminous characteristics.
RESULTS IN PHYSICS
(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
Kun Wang, Chad M. Parish, Kevin G. Field, Lizhen Tan, Yutai Katoh
Summary: In this study, a reduced activation ferritic/martensitic steel Eurofer97 was neutron irradiated in the High Flux Isotope Reactor (HFIR) up to 72 dpa at around 300 degrees C. Advanced analytical scanning transmission electron microscopy and conventional transmission electron microscopy were used to investigate the radiation-induced segregation and phase instability behavior. The results showed that amorphization occurred in M23C6 carbides and Cr-rich clusters formed in the matrix, near the lath boundaries and close to the M23C6 carbides after neutron irradiation.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Jose David Arregui-Mena, David A. Cullen, Robert N. Worth, Singanallur V. Venkatakrishnan, Matthew S. L. Jordan, Michael Ward, Chad M. Parish, Nidia Gallego, Yutai Katoh, Philip D. Edmondson, Nassia Tzelepi
Summary: Porosity can heavily influence the properties of nuclear-grade graphite, and electron tomography is able to visualize the sub-micron pores in three dimensions. This research demonstrates the 3D structure of both native and irradiation-induced nano-cracks in graphite, as well as the unique characteristics of graphite such as pore structure. The technique could also be useful for molecular dynamic simulations and experimental techniques related to irradiated graphite and other nuclear porous carbon-based materials.
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
Jacob Startt, Remi Dingreville, Stephen Raiman, Chaitanya Deo
Summary: Ni-Cr alloys exhibit oscillatory segregation behaviors near low index surfaces, with the amount of charge on the Cr atom and the contraction in size of the Cr atom in the second layer of the surface playing key roles.
Article
Materials Science, Ceramics
Adam Bratten, Visharad Jalan, Meng Shi, Tyler Gerczak, Haiming Wen, Peter Doyle, Haiyan Zhao, Xiaoqing He
Summary: Surrogate tristructural-isotropic (TRISO)-coated fuel particles were oxidized in 0.2 kPa O-2 to examine the behavior of the SiC layer. The analysis of the resulting SiO2 layers showed a majority of smooth, amorphous SiO2 with a constant thickness indicative of passive oxidation. The activation energy for oxide growth was consistent across all temperatures and the presence of irregular grain size influenced the oxidation response of the SiC layer.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2023)
Article
Materials Science, Multidisciplinary
Peter Doyle, Juri Stuckert, Mirco Grosse, Martin Steinbrueck, Andrew T. Nelson, Jason Harp, Kurt Terrani
Summary: The QUENCH-19 experiment was a full-bundle test of accident-tolerant fuel cladding, specifically the B136Y3 alloy. Compared to the ZIRLO cladding in QUENCH-15, the B136Y3 cladding in QUENCH-19 released significantly less H2 and reached a lower maximum temperature. No breakaway oxidation was observed in QUENCH-19. The experiment suggests that Fe-CrAl cladding can chemically survive loss-of-coolant accidents followed by rapid ECCS quench if the correct geometry and core design are present.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Chemistry, Analytical
Benjamin T. T. Manard, Hunter B. B. Andrews, C. Derrick Quarles Jr, Veronica C. C. Bradley, Peter Doyle, N. Alex Zirakparvar, Daniel R. R. Dunlap, R. R. Hexel
Summary: Laser-induced breakdown spectroscopy (LIBS) is used to characterize coatings on surrogate fuel particles. LIBS can directly analyze the sample surface, making it a viable technique for analyzing small, multilayered particles. In this study, LIBS successfully discerns small layers, detects the location of carbon and oxygen layers, and provides fast 2-D mapping and rapid depth profiling.
JOURNAL OF ANALYTICAL ATOMIC SPECTROMETRY
(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)
