Article
Materials Science, Multidisciplinary
Xinyu Huo, Peng Chen, Simanta Lahkar, Mingjiang Jin, Xiaocang Han, Yuanwei Song, Xiaodong Wang
Summary: This study investigates the formation mechanism of the R-phase and the mechanism of ultrahigh intrinsic friction in NiTi alloys. The results show that Ni segregation is responsible for the formation of the R-phase, and the volume fraction of nanodomain boundaries determines the performance of ultrahigh intrinsic friction.
Article
Nanoscience & Nanotechnology
Kengfeng Xu, Jiao Luo, Cong Li, Yulu Shen, Chaojun Li, Xiao Ma, Miaoquan Li
Summary: R and B2 nano-domains are introduced in NiTi shape memory alloy, leading to high superelastic stability. The study proposes a three-step shear stress-induced martensitic transformation, explaining the transformation behavior in as-deformed and as-aged NiTi. The research suggests inhibiting the formation of transformation-induced stacking faults as a way to improve superelastic stability.
SCRIPTA MATERIALIA
(2022)
Article
Materials Science, Multidisciplinary
Jeong Min Park, Peyman Asghari-Rad, Alireza Zargaran, Jae Wung Bae, Jongun Moon, Hyeonseok Kwon, Jungho Choe, Sangsun Yang, Ji-Hun Yu, Hyoung Seop Kim
Summary: Selective laser melting (SLM) technology offers unprecedented advantages in improving the mechanical properties of metals and alloys through unique dislocation network and solute segregation.
Article
Materials Science, Multidisciplinary
O. Kachko, A. Puype, D. Terentyev, M. Duerrschnabel, M. Klimenkov, R. H. Petrov
Summary: Two RAFM alloys with improved microstructures and mechanical properties were designed and tested, showing higher yield and tensile strength without sacrificing impact toughness. This improvement was achieved through dedicated chemical and thermal treatments, resulting in refined grain and subgrain size and a high density of dislocations. TEM investigation was conducted to quantitatively describe the microstructural parameters and calculate the strengthening contribution of each microstructural feature.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Metallurgy & Metallurgical Engineering
Li-dong Xia, Hao Chen, Zhi-gang Yang, Chi Zhang
Summary: Helium ion irradiation at 350 degrees C was performed to study the equilibrium segregation and radiation-induced segregation of Cr at grain boundaries in reduced activation ferritic/martensitic steels. The Cr concentration at grain boundaries was measured and analyzed, with results indicating that as temperature rises, equilibrium Cr segregation decreases monotonically, while RIS of Cr has a bell-shaped profile, increasing first and then decreasing. It was also found that at low and high temperatures, equilibrium segregation of Cr is higher than RIS; at intermediate temperatures, equilibrium Cr segregation is lower than RIS.
JOURNAL OF IRON AND STEEL RESEARCH INTERNATIONAL
(2021)
Article
Materials Science, Multidisciplinary
Meimei Li, Zuotao Zeng, Wei-Ying Chen
Summary: This study investigates the carbon transfer and its impact on the microstructure and tensile properties of Grade 91 (G91) ferritic-martensitic steel in sodium environments. Experimental and theoretical analyses reveal the carburization-decarburization process of G91 steel and its effects on grain growth and strength reduction. The findings provide important insights for predicting the integrity of reactor components and designing new alloys in sodium-cooled fast reactors.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Chemistry, Physical
Yanqi Luo, Shuchen Zhang, Jia-Shiang Chen, Xuedan Ma, Ke Ma, Junjing Deng, Yi Jiang, Luxi Li, Barry Lai, Si Chen, Sarah Wieghold, Letian Dou
Summary: In this study, the degradation pathways of two-dimensional perovskite semiconductor materials under UV exposure were investigated using nano-XRF. The results showed that the loss of iodine was monotonically decreasing with increasing perovskite dimensionality, while bromine was relatively more stable, but diffused to the previously iodine-rich regime. Combining nano-XRF and XAS, it was found that crystals with dimensionality greater than 1 underwent structural reconfiguration after UV exposure.
Article
Materials Science, Multidisciplinary
Xu Chen, Shaowen Peng, Ye Liu, Song Bai, Lin Zhang, Shuang He, Oleg I. Gorbatov, Xuanhui Qu
Summary: Ductility deterioration induced by L21-Ni2AlTi precipitates in aged ferritic alloys was systematically examined using scanning transmission electron microscopy, mechanical tests, and first-principles thermodynamic calculations. Experimental studies showed that the presence of B2-NiAl and L21-Ni2AlTi precipitates in the alloy resulted in higher strength and hardness compared to the alloy with only NiAl precipitates, but a significant decrease in elongation-to-failure, indicating obvious ductility deterioration. Theoretical analysis revealed the intrinsic brittleness of L21-Ni2AlTi phase and L21-Ni2AlTi/BCC-Fe interface.
JOURNAL OF MATERIALS RESEARCH AND TECHNOLOGY-JMR&T
(2023)
Article
Nanoscience & Nanotechnology
Tomohiko Hojo, Motomichi Koyama, Bakuya Kumai, Yuki Shibayama, Ayumi Shiro, Takahisa Shobu, Hiroyuki Saitoh, Saya Ajito, Eiji Akiyama
Summary: The origins of the superior work hardening capability of medium manganese (M-Mn) and conventional transformation-induced plasticity-aided bainitic ferrite (TBF) steels of similar tensile strength and elongation are investigated. The work hardening capability of M-Mn steel is attributed to high rates of martensitic transformation and dislocation accumulation in retained austenite, while the work hardening capability of TBF steel is attributed to high austenite phase stability and resistance to slip deformation.
SCRIPTA MATERIALIA
(2022)
Article
Materials Science, Multidisciplinary
Y. L. Zhaoa, F. L. Meng, T. Yang, J. H. Luan, S. F. Liu, G. M. Yeli, W. T. Lin, W. H. Liu, X. J. Liu, C. T. Liu, J. J. Kai
Summary: In this study, a novel L1 2 -strengthened HEA alloy was irradiated with He ions, and the microstructural stability and radiation-induced segregation were investigated using TEM and APT. The results showed that the irradiated HEA exhibited improved irradiation resistance and reduced bubble size, attributed to the trapping efficiency of the precipitate/matrix interface and the interface's enhanced capability for damage elimination. The irradiation-induced diffusion and precipitation dissolution and re-precipitation also contributed to the alloy's radiation tolerance and self-healing effect.
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY
(2023)
Article
Materials Science, Multidisciplinary
Taotao Wang, Xiangxiang Rao, Qiang Zhang, Daqiang Jiang, Yang Ren, Lishan Cui, Kaiyuan Yu
Summary: The temperature dependence of the critical stress of the R -> B19' transformation in NiTi shape memory alloys has been found to be negative in this study, in contrast to previous reports. This discovery calls for a reevaluation of this transformation.
MATERIALS RESEARCH LETTERS
(2023)
Article
Nanoscience & Nanotechnology
Elango Chandiran, Yukiko Ogawa, Rintaro Ueji, Alok Singh, Hidetoshi Somekawa
Summary: The effects of different crystallographic orientations of the grains on damping capacity (tan8) in magnesium alloys were investigated. The results showed that the grain orientation had a significant impact on the damping capacity of pure magnesium and Mg-Sc alloy. The absence of the solute atom Sc resulted in higher damping capacity in pure magnesium compared to the Mg-Sc alloy.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
(2023)
Article
Materials Science, Multidisciplinary
Daniel Vizoso, Chaitanya Deo, Remi Dingreville
Summary: Radiation-induced segregation is a phenomenon where elements in alloys redistribute under irradiation. This study examines the effects of dose, dose rate, and particle type on radiation-induced segregation behavior in a model binary alloy using a phase-field model. The results show that dose rate and particle type affect the amount of solute segregation, and materials exposed to higher dose rates are less susceptible to solute segregation.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Materials Science, Multidisciplinary
Hyosim Kim, Jonathan G. Gigax, Osman El-Atwani, Matthew R. Chancey, Jon K. Baldwin, Yongqiang Wang, Stuart A. Maloy
Summary: The irradiation of ferritic-martensitic (F/M) HT9 and fully ferritic HT9 alloys revealed different void swelling behaviors under carbon contamination, indicating a correlation with the stability of carbides within the materials.
MATERIALS CHARACTERIZATION
(2021)
Article
Nanoscience & Nanotechnology
Chao Lv, Guiji Wang, Xuping Zhang, Bingqiang Luo, Ning Luo, Haifeng Song, Fengchao Wu, Heng-an Wu, Fuli Tan, Jianheng Zhao, Cangli Liu, Chengwei Sun
Summary: The ground state structure of NiTi martensite in experiments and calculations is still a matter of dispute. In this study, based on previous experiments by Waitz et al. (2004, 2007), first principle calculations were used to investigate the influence of (001) twin interface and thickness on the stability of NiTi martensite. The results showed that the (001) martensitic twins observed in the experiments can be represented by the interface of twinned supercell-1 (TSC-1), which has similar structural properties to B33. The energy per atom for TSC-1 was found to be in between that of B19 & PRIME; and B33, indicating a possible energy barrier between TSC-1 and B33.
SCRIPTA MATERIALIA
(2022)
Article
Materials Science, Multidisciplinary
Chao Yang, Tristan Olsen, Miu Lun Lau, Kassiopeia A. Smith, Khalid Hattar, Amrita Sen, Yaqiao Wu, Dewen Hou, Badri Narayanan, Min Long, Janelle P. Wharry, Hui Xiong
Summary: Understanding the evolution of structure and morphology in nanomaterials is crucial for controlling their functionality. In this study, the effects of irradiation on the morphology and structure of amorphous and anatase TiO2 nanotubes were investigated. The anatase TiO2 nanotubes showed stability under irradiation due to their grain boundaries and surfaces, while the amorphous TiO2 nanotubes underwent irradiation-induced crystallization, with partially crystallized tubes bending due to internal stresses. These findings provide a new pathway for controlling the structure and morphology of energy storage materials.
JOURNAL OF MATERIALS RESEARCH
(2022)
Article
Nanoscience & Nanotechnology
Chao Yang, Yash Pachaury, Anter El-Azab, Janelle Wharry
Summary: Vacancies have no significant effect on martensitic transformation, while voids activate the transformation by inducing shear strain accumulation due to dislocation pileup. The larger the void, the more pronounced the effect.
SCRIPTA MATERIALIA
(2022)
Article
Materials Science, Multidisciplinary
Yash Pachaury, Tomohisa Kumagai, Janelle P. Wharry
Summary: This article presents a statistical method for analyzing continuously distributed data of irradiated FeCrAl alloys using Energy Dispersive X-ray Spectroscopy (EDS). By using probability distribution functions and covariance functions, the effects of alloy composition and irradiation dose on the spatial distribution and length scale of composition fluctuations were investigated.
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
Haozheng J. Qu, Janelle P. Wharry
Summary: In this study, the correlation between grain orientation, grain boundaries, and hardening from TGCISCC propagation was investigated by nanoindentation mapping and scanning electron microscopy. The results showed that the hardness of individual grains does not control TGCISCC propagation, but localized strain hardening at the crack tip was observed.
Article
Materials Science, Multidisciplinary
Priyam Patki, Yaqiao Wu, B. Chad Hornbuckle, Kristopher A. Darling, Janelle P. Wharry
Summary: This study explored the effects of coupled deformation and irradiation extremes on Ta phase evolution in Cu-10at.%Ta nanocomposite. The findings suggest that after irradiation-induced dissolution of Ta nanoparticles, deformation-induced Ta nanoparticle nucleation and growth along grain boundaries may stabilize or rejuvenate the nanoparticles in extreme environments.
Article
Physics, Applied
Brandon Dzuba, Trang Nguyen, Amrita Sen, Rosa E. Diaz, Megha Dubey, Mukesh Bachhav, Janelle P. Wharry, Michael J. Manfra, Oana Malis
Summary: Growth of wurtzite ScxAl1-xN (x<0.23) on c-plane GaN at high temperatures alters the lattice constants due to defects, while ScAlN grown below a certain temperature exhibits uniform alloy distribution and reduced defect density. The lattice constant of low-temperature ScAlN varies with composition and can be used to estimate alloy composition. Lattice-matched Sc0.18Al0.82N/GaN multi-quantum wells grown under these conditions show strong near-infrared absorption lines, confirming their advantageous optical and electronic properties.
JOURNAL OF APPLIED PHYSICS
(2022)
Article
Nanoscience & Nanotechnology
Caleb Clement, Sowmya Panuganti, Patrick H. Warren, Yangyang Zhao, Yu Lu, Katelyn Wheeler, David Frazer, Donna P. Guillen, David W. Gandy, Janelle P. Wharry
Summary: This study compares the response of PM-HIP alloys and forged alloys under neutron irradiation. The results show that PM-HIP alloys have better resistance to irradiation and less hardening. These findings provide hope for the qualification of PM-HIP alloys for nuclear applications.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
(2022)
Review
Chemistry, Physical
Cyrus Koroni, Tristan Olsen, Janelle P. Wharry, Hui Xiong
Summary: Amorphous ceramics are a class of materials with unique properties and functionalities. While irradiation is commonly associated with disorder, it has been observed that irradiation can induce crystallization in amorphous ceramics. This perspective provides a summary and review of examples from the literature on irradiation-induced amorphous-to-crystalline phase transformations in ceramics, highlighting the influential irradiation conditions, material parameters, and discussing the impact on material properties. Future research directions to harness these transformations for tailored material behavior are also presented.
Article
Materials Science, Multidisciplinary
Priyam Patki, Timothy J. Pownell, Yerik Bazarbayev, Dalong Zhang, Kevin G. Field, Janelle P. Wharry
Summary: This study systematically reports the grain boundary radiation-induced segregation (RIS) and its mechanisms in FeCrAl alloys, emphasizing the need to consider RIS implications on corrosion and oxidation susceptibility in alloy design.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Nanoscience & Nanotechnology
Alejandro Hinojos, Daniel Hong, Hariharan Sriram, Longsheng Feng, Chao Yang, Janelle P. Wharry, Xuesong Gao, Khalid Hattar, Nan Li, Jeremy E. Schaffer, Yunzhi Wang, Michael J. Mills, Peter M. Anderson
Summary: Implantation of Ni50.5Ti49.5 wire with low doses of 30 MeV Ni6+ ions can systematically alter the pseudoelastic response, with extreme changes in nanoindentation load, hysteresis, and recoverable displacement occurring at a depth of 3.6 μm below the implantation surface. These changes are attributed to amorphous clusters that constrain the stress-induced B2-B19' phase transformation. Simulations support this by showing the refinement of martensite caused by nm-scale defects. These results suggest that ion implantation could expand the processing and performance capabilities of NiTi.
SCRIPTA MATERIALIA
(2023)
Article
Multidisciplinary Sciences
Janelle P. Wharry, Caleb D. Clement, Yangyang Zhao, Katelyn Baird, David Frazer, Jatuporn Burns, Yu Lu, Yaqiao Wu, Collin Knight, Donna P. Guillen, David W. Gandy
Summary: This article presents a comprehensive mechanical testing data archive of nuclear structural alloys fabricated by powder metallurgy with hot isostatic pressing (PM-HIP) after neutron irradiation. The data includes uniaxial tensile tests, fractography analysis, and nanoindentation. By openly sharing this valuable dataset, researchers can use the data to populate material performance databases, validate models, design experiments, and qualify PM HIP techniques for nuclear applications.
Article
Materials Science, Multidisciplinary
Patrick H. Warren, Caleb D. Clement, Chao Yang, Amrita Sen, Wei-Ying Chen, Yaqiao Wu, Ling Wang, Janelle P. Wharry
Summary: The objective of this study is to understand the evolution of irradiation-induced and assisted defects in binary body center cubic (bcc) Fe-based alloys. Three alloys (Fe9.5%Cr, Fe-4.5%P, and Fe-2.3%N) with varying solute sizes and positions were selected for investigation. The results showed that the presence of different solute species affected the development of irradiation-induced defects in the alloys, with undersized substitutional solutes (e.g., P) hindering their formation and oversized substitutional or interstitial solutes (e.g., Cr and N) potentially suppressing dislocation loop development.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Materials Science, Multidisciplinary
Chao Yang, Janelle P. Wharry
Summary: The effect of vacancies, interstitials, and antisite defects on stress-induced phase transformation in equiatomic NiTi alloy was investigated using molecular dynamics simulation. The results show that all defects suppress the transformation, with vacancy clusters having the greatest suppressive effect and antisite defects having the least. The responsible mechanisms are grain boundary pinning and chemical disordering.
Article
Materials Science, Multidisciplinary
Haozheng J. Qu, Fei Tao, Nianju Gu, Timothy Montoya, Jason M. Taylor, Rebecca F. Schaller, Eric Schindelholz, Janelle P. Wharry
Summary: This study investigates the influence of crystallography on transgranular chloride-induced stress corrosion cracking (TGCISCC) in arc welded 304L austenitic stainless steel. The crack propagation can be explained by mechanical arguments, and the competition between mechanical, crystallographic, and corrosion factors is discussed in relation to crack behavior at grain boundaries.
NPJ MATERIALS DEGRADATION
(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)
