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
Chemistry, Analytical
Elisabetta Medina, Enrico Sangregorio, Andreo Crnjac, Francesco Romano, Giuliana Milluzzo, Anna Vignati, Milko Jaksic, Lucia Calcagno, Massimo Camarda
Summary: To explore the radiation tolerance of SiC sensors, this study used the Ion Microprobe Chamber to expose small areas within the same device to different ion beams, evaluating and comparing effects. The sensors tested were PIN diodes with ultrathin free-standing membranes developed by STLab and SenSiC, demonstrating changes in charge transport properties after localized proton irradiation at both room temperature and 500 degrees C.
Article
Materials Science, Ceramics
Seong-Gun Bae, Minkyoung Oh, Yoonjoo Lee, Sanghun Kim, Yeong-Geun Jeong, Jung-Min Lee, Jungil Kim, Dong-Geun Shin
Summary: This study aims to improve the high-temperature creep characteristics of polycrystalline silicon carbide fibers by dispersing hafnium carbide nanocrystals in crystalline silicon carbide fibers. The results confirmed that hafnium carbide was uniformly dispersed, and that the crystal size grew to approximately 40 nm at a sintering temperature of 2000 degrees C.
CERAMICS INTERNATIONAL
(2022)
Article
Materials Science, Ceramics
Hao Zhang, Min Ge, Huifeng Zhang, Weijia Kong, Shouquan Yu, Weigang Zhang
Summary: The study synthesized continuous SiC-ZrB2 composite ceramic fibers with excellent mechanical properties and high-temperature creep resistance.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2021)
Review
Chemistry, Physical
Alexander A. Lebedev, Vitali V. Kozlovski, Klavdia S. Davydovskaya, Mikhail E. Levinshtein
Summary: Silicon carbide shows good radiation hardness against electron and proton irradiation, with the main compensation mechanism being the formation of deep acceptor levels. The probability of these centers forming decreases with increasing irradiation temperature, leading to a significant reduction in carrier removal rate. This further establishes silicon carbide as a promising material for high-temperature electronics devices.
Article
Materials Science, Ceramics
Pavol Sajgalik, Zanlin Cheng, Xuxu Han, Chengyu Zhang, Ondrej Hanzel, Jaroslav Sedlacek, Tatyana Orlova, Maksym Zhukovskyi, Alexander S. Mukasyan
Summary: The high-temperature compression creep properties of additive-free beta/alpha silicon carbide ceramics fabricated by rapid hot pressing were investigated, showing the ceramics had the lowest creep rate reported in the literature within certain temperature and pressure ranges. The average creep activation energy and stress exponent remained constant along the whole range of investigated parameters, suggesting a creep mechanism involving GB sliding accommodated by GB diffusion and beta-alpha SiC phase transformation.
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
(2022)
Article
Materials Science, Multidisciplinary
Subing Yang, Yuki Nakagawa, Minako Kondo, Tamaki Shibayama
Summary: Anisotropic swelling in hexagonal alpha-SiC induced by irradiation was found to degrade the mechanical properties of the material. By introducing an anisotropic swelling condition in 4H-SiC using selected-area He+ irradiation, researchers observed an anisotropic distribution of defects which could potentially enhance the understanding of SiC's mechanical properties.
Article
Computer Science, Information Systems
Liansheng Zhao, Yidan Tang, Yun Bai, Menglin Qiu, Zhikang Wu, Yu Yang, Chengyue Yang, Xiaoli Tian, Xinyu Liu
Summary: This study investigated the defects and electrical characteristics of 4H-SiC JBS diodes irradiated by 2 MeV protons at temperatures ranging from 100 to 400 K. It was found that as the irradiation temperature increased, the on-resistance decreased, leakage current increased, and DLTS spectrum intensity decreased.
Article
Materials Science, Ceramics
Jean-Marc Costantini, Joel Ribis
Summary: This study investigates the damage induced in 3C-SiC epilayers on a silicon wafer by 2.3-MeV Si ion irradiation for different fluences, and deduces the threshold energy densities and irradiation doses for dislocation loop formation and amorphous phase transformation. The role of electronic excitations on the damage recovery at high fluence is also addressed for both SiC and Si.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2021)
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, Ceramics
Shanshan Xu, Ce Zheng, Yichun Bi, Qingping Mao, Hailong Qin, Xiaoqiang Li
Summary: SiC/SiC composites are promising materials for nuclear systems, and SiC fibers play a critical role in the performance of these composites. This study investigated the microstructural evolution of Cansas-III SiC fibers under temperature effects using in-situ transmission electron microscopy. The results showed that at room temperature, the SiC fibers experienced heterogeneous amorphization and became completely amorphous at a certain dose. At temperatures above the critical temperature for crystalline-to-amorphous transition, the fibers underwent carbon packet disappearance and nano-grain growth. Possible mechanisms were discussed.
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
(2023)
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
Physics, Applied
Hiroki Fujimoto, Takuma Kobayashi, Mitsuru Sometani, Mitsuo Okamoto, Takayoshi Shimura, Heiji Watanabe
Summary: The impact of NO nitridation on SiO2/SiC interfaces was studied and it was found that while nitridation can passivate electron traps, it also induces additional traps and increases the sensitivity to UV light.
APPLIED PHYSICS EXPRESS
(2022)
Article
Materials Science, Ceramics
Xinwei Yuan, Sosuke Kondo, Kiyohiro Yabuuchi, Hao Yu, Yasuyuki Ogino, Ryuta Kasada
Summary: In this study, the effect of annealing temperature on the proportion of fiber shrinkage and swelling in SiC fiber-reinforced matrix composites (SiCf/SiC) was investigated. The results showed that the compressive displacement of the fibers increased by more than 1.5 times after annealing, and significant swelling was observed. This study provides insights into the mechanism of irradiation-induced fiber amorphization and can be useful for the development of improved SiCf/SiC materials.
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
(2023)
Article
Engineering, Electrical & Electronic
Alexander A. Lebedev, Vitali V. Kozlovski, Michael E. Levinshtein, Anton E. Ivanov, Klava S. Davydovskaya
Summary: The study found that high-temperature irradiation with 15 MeV protons significantly affects the parameters of high-voltage 4H-SiC Schottky diodes, with dose and irradiation temperature causing changes in forward current and cutoff voltage.
SOLID-STATE ELECTRONICS
(2021)
Editorial Material
Instruments & Instrumentation
T. Kubley, F. Naab, O. Toader, G. Was
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS
(2019)
Article
Materials Science, Multidisciplinary
D. C. Johnson, B. Kuhr, D. Farkas, G. S. Was
Article
Materials Science, Multidisciplinary
Wenjun Kuang, Gary S. Was
Article
Materials Science, Multidisciplinary
Bryan Kuhr, Diana Farkas, Ian M. Robertson, Drew Johnson, Gary Was
METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE
(2020)
Article
Materials Science, Multidisciplinary
Wenjun Kuang, Gary S. Was
Article
Materials Science, Multidisciplinary
Justin Hesterberg, Zhijie Jiao, Gary S. Was
JOURNAL OF NUCLEAR MATERIALS
(2019)
Article
Materials Science, Multidisciplinary
Stephen Taller, Zhijie Jiao, Kevin Field, Gary S. Was
JOURNAL OF NUCLEAR MATERIALS
(2019)
Review
Materials Science, Multidisciplinary
G. S. Was, D. Petti, S. Ukai, S. Zinkle
JOURNAL OF NUCLEAR MATERIALS
(2019)
Editorial Material
Materials Science, Multidisciplinary
Gary S. Was
JOURNAL OF NUCLEAR MATERIALS
(2019)
Article
Materials Science, Multidisciplinary
Peng Wang, Slavica Grdanovska, David M. Bartels, Gary S. Was
JOURNAL OF NUCLEAR MATERIALS
(2020)
Article
Materials Science, Multidisciplinary
Stephen Taller, Gary S. Was
Article
Instruments & Instrumentation
Stephen Taller, Fabian Naab, Gary S. Was
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS
(2020)
Article
Materials Science, Multidisciplinary
Miao Song, Kevin G. Field, Richard M. Cox, Gary S. Was
JOURNAL OF NUCLEAR MATERIALS
(2020)
Article
Materials Science, Multidisciplinary
Logan N. Clowers, Zhijie Jiao, Gary S. Was
Summary: Three ferritic/martensitic alloys were irradiated with single, dual, and triple ion beams to study cavity evolution. Co-injection of hydrogen with helium increased cavity number density and size, leading to higher swelling. F82H alloy exhibited the lowest swelling due to high sink strength, while CNA3 alloy showed higher swelling than F82H due to lower sink strength caused by precipitation dissolution.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Materials Science, Multidisciplinary
J. Bowman, P. Wang, G. S. Was, M. Bachhav, A. T. Motta
Summary: Samples of Zircaloy-4 were ion irradiated at various doses and temperatures to study the amorphization and dissolution behavior of second-phase precipitates. The results showed that similar amorphization morphology occurred under proton irradiation as under neutron irradiation near the critical temperature for amorphization. However, the rate of amorphous layer advancement was slower under proton irradiation and did not lead to complete amorphization. The critical temperature for bulk amorphization primarily depended on the displacement cascade density achievable with the irradiating particle and secondarily with dose rate.
JOURNAL OF NUCLEAR MATERIALS
(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)