Article
Materials Science, Ceramics
Kuo-Hao Lee, Yongjian Yang, Linfeng Ding, Benedikt Ziebarth, Mark J. Davis, John C. Mauro
Summary: The addition of alkali ions lowers the yield stress and changes the pressure dependence of shear modulus in multicomponent borosilicate glasses. Shear-induced densification is observed in both glasses, with 5-coordinated Si being the dominant mechanism for densification at high pressures. Boron atoms tend to experience plastic deformation in Borofloat 33, while plastic deformation occurs around alkali-rich regions in N-BK7, indicating different atomic-scale deformation mechanisms in these two glasses.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2021)
Article
Materials Science, Ceramics
Chengyue Li, Qinghui Xiao, Yang Fu, Yunhao Liang, Chuanlong Liu, Yijun Zhuang, Libin Xia
Summary: Eu2+-doped SiO2-SrO-B2O3 glasses exhibit broad luminescence band with 0.4 mol% Eu2+ being the optimum doping concentration. The absorption and emission spectra show redshift with increasing Eu2+ concentration, while concentration quenching occurs due to electric dipole-dipole interaction. The luminescence intensity decreases with increasing temperature and the chromaticity shift is lower than Eu2+-doped commercial phosphors.
JOURNAL OF NON-CRYSTALLINE SOLIDS
(2021)
Article
Materials Science, Multidisciplinary
L. T. Chen, X. T. Ren, Y. N. Mao, J. J. Mao, X. Y. Zhang, T. T. Wang, M. L. Sun, T. S. Wang, M. M. Smedskjaer, H. B. Peng
Summary: The study investigated the effects of irradiation on sodium borosilicate glasses and International Simple Glass (ISG), revealing the saturation of hardness, modulus, and volume changes at a certain irradiation dose, and a significant increase in crack initiation resistance (CR). The structural changes in borosilicate glasses were also examined, showing a transformation of BO4 to BO3 groups upon irradiation with heavy ions. These findings suggest the importance of boron structures in controlling the macroscopic radiation effects on glasses.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Sathya Narayanasamy, Patrick Jollivet, Christophe Jegou, Melanie Moskura, Abdesselam Abdelouas, Thibault Charpentier, Frederic Angeli
Summary: A study was conducted on the alteration of a Na-alumino-borosilicate glass and its Ca-doped counterpart in vapor phase and aqueous medium. The results showed differences in alteration kinetics, behavior of elements, and gel layer structure between the two alteration media, and provided insights into the mechanisms of glass alteration in these media.
NPJ MATERIALS DEGRADATION
(2022)
Article
Materials Science, Ceramics
Fenglin Gu, Qian Qiao, Jiaxin Yu, Hongtu He
Summary: This study investigated the effect of mechanical interactions such as contact pressure, sliding speed, and sliding time on subsurface densification of borosilicate glass. It was found that contact pressure had the strongest influence on subsurface densification. The results provide deeper insights into surface wear and subsurface densification of silicate glass materials during manufacturing and serving process.
JOURNAL OF NON-CRYSTALLINE SOLIDS
(2021)
Article
Materials Science, Ceramics
Seyed Sadegh Khayat Ardestani, Valiollah Dashtizad, Ali Kaflou
Summary: The study examined the effects of process variables including temperature, time, and atmosphere on the macroscopic soundness of glass-metal seals, particularly focusing on the sealing of borosilicate glass to Kovar alloy. The research found that by limiting the sealing temperature and time, the tendency for bubble formation could be significantly decreased. Additionally, the soundness of the tubular butt joints was found to have an inverse correlation with the thickness of the metal tube and a direct correlation with the thickness of the glass tube. Fracture tests on tubular seals cooled at common rates revealed that failures often occurred inside the glass, characterized by circular fractures parallel to the seal interface. Structural analysis suggested compositional segregation in the glass near the interface and the presence of fayalite second phases nucleated on the interface.
CERAMICS INTERNATIONAL
(2021)
Article
Materials Science, Multidisciplinary
Jae -Young Pyo, Wooyong Um, Jong Heo
Summary: This study investigated the effects of adding MnO and ZnO to a fabricated nuclear waste glass on the crystallization of molybdates and structure of the glass. The results confirmed that the addition of MnO and ZnO increased the solubility of Mo in the glass and inhibited the formation of alkali molybdate crystals. The addition of MnO further improved the solubility of Mo. These findings are important for enhancing the chemical durability of the glass.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Materials Science, Ceramics
Shuqing Fang, Yangshan Sun, Liang Feng, Qi Liu, Zhengyi Zhang, Na Han, Pingping Wang, Yuxiao Zhou, Jing Wang, Chong Zhang, Tianhe Wang
Summary: This article reports a novel method for immobilization of Cs-137 by sintering Cs-polluted soil and borosilicate glass powder to form a pollucite-based glass crystalline material. The method shows lower formation temperatures and improved chemical durability compared to conventional sintering methods. This study not only presents an improved technique for Cs-137 immobilization but may also provide a methodology for immobilization of other potential radioactive species.
JOURNAL OF NON-CRYSTALLINE SOLIDS
(2022)
Article
Materials Science, Ceramics
K. L. Skerratt-Love, J. L. George, A. M. T. Bell, F. Sweeney, D. Cutforth, C. E. Lonergan, D. R. Dixon, A. A. Kruger, P. A. Bingham
Summary: This research investigates the influence of P2O5 additions on the properties and structure of SiO2-B2O3-Na2O glasses used for radioactive waste immobilization. The study reveals that the addition of P2O5 leads to changes in viscosity, glass transition temperature, and crystallization behavior. X-ray diffraction analysis confirms the presence of crystalline phases at specific P2O5 concentrations. The findings highlight the importance of P2O5 content in controlling the properties and structure of the glasses. Overall, this research provides valuable insights for the development of effective waste immobilization materials.
JOURNAL OF NON-CRYSTALLINE SOLIDS
(2023)
Article
Materials Science, Ceramics
Kuo-Hao Lee, Yongjian Yang, Linfeng Ding, Benedikt Ziebarth, John C. Mauro
Summary: In this study, hot-compression of two multicomponent borosilicate glasses, Borofloat33 and N-BK7, was investigated using molecular dynamics simulations. The results showed that the improvement of fracture toughness (KIC) was mainly influenced by the change in Young's modulus under pressure, with Boro33 showing more effective enhancement due to its higher concentration of 3-coordinated boron (B-3) facilitating densification.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2022)
Article
Materials Science, Ceramics
Peng Lv, Zhao Sun, Fugang Wang, Yang Yu, Fan Yang, Shengjun Yue, Mattias Eden, Liang Chen, Tieshan Wang
Summary: In this study, the impact of the glass network-modifier cation field strength on ion irradiation-induced mechanical property changes in borosilicate glasses was examined. It was found that the proportion of four-coordinated boron (B-[4]) species and B-[4]-O-Si linkages in the glass network correlated linearly with the field strength of the modifying cations. The level of irradiation damage also increased linearly with the fraction of B-[4]-O-Si linkages. These findings highlight the potential of using borosilicate glasses with high-field strength cations to enhance radiation resistance.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2023)
Article
Materials Science, Ceramics
Rajesh Kumar, Amreen Jan, Mathieu Bauchy, N. M. Anoop Krishnan
Summary: Using molecular dynamics simulations, the study observed that irradiation increases disorder in short- and medium-range order in borosilicate glasses. The volumetric response of borosilicate glasses under irradiation shows a composition-dependent transition, with borate-rich compositions tending to swell and silica-rich glasses tending to densify. The increase in disorder in medium-range order plays a significant role in governing the volumetric changes in the irradiated structure.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2021)
Article
Materials Science, Multidisciplinary
A. Manivannan, G. Saravanan, P. Ravisankar, Soumee Chakraborty, Kitheri Joseph, V Jayaraman
Summary: Enthalpy increment data were obtained for borosilicate and doped borosilicate glasses containing uranium oxides and plutonium surrogates. The specific heat of the glasses was calculated and compared, and the thermal stability and network structure of the glasses were investigated using micro Raman spectroscopy.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Materials Science, Ceramics
Jie Fu, Shiquan Liu, Haixiang Zhang, Shenghong Shi, Jianzhong Zhang, Yang Shen
Summary: In this study, Fe2O3 and TiO2 were used as colorants in borosilicate glass to analyze their influence on the glass structure. Fe2O3 decreased the connectivity of the silica network, while TiO2 had a larger depolymerization effect. Iron ions improved the water resistance of the glass, while TiO2 had the opposite effect. The glass sample containing both Fe2O3 and TiO2 exhibited the best UV-blocking ability and water resistance.
CERAMICS INTERNATIONAL
(2023)
Article
Engineering, Mechanical
Qian Qiao, Hongtu He, Jiaxin Yu, Yafeng Zhang, Huimin Qi
Summary: Machine learning is used to predict the mechanochemical wear properties of borosilicate and phosphate glass, with artificial neural network showing the highest prediction accuracy. The study also highlights the influence of training data repetition and hidden layers on the prediction accuracy of the ANN algorithm.
Article
Materials Science, Multidisciplinary
Sathya Narayanasamy, Patrick Jollivet, Loryelle Sessegolo, Frederic Angeli, Abdesselam Abdelouas
Summary: The study investigated the effects of temperature and relative humidity on the vapor hydration of AVM6 glass, revealing that the secondary phase precipitates varied with temperature and relative humidity, while the morphology of the altered layer remained similar at different temperatures. The findings suggest that network-hydrolysis is the predominant rate controlling mechanism at temperatures between 50-90 degrees C.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Christophe Jegou, Sathya Narayanasamy, Frederic Angeli
Summary: The hydration of S0N68 glass, a non-radioactive surrogate for R7T7 glass, was studied at temperatures between 30 and 70 degrees C with a relative humidity of 95% for 6 months. The hydration thickness increased with temperature and the temperature dependence of hydration rates followed Arrhenius law, leading to determination of an activation energy of 62 +/- 13 kJ/mol, indicating a mechanism involving hydrolysis of the silicate bonds.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Ceramics
Jincheng Du, Xiaonan Lu, Stephane Gin, Jean-Marc Delaye, Lu Deng, Melanie Taron, Nicolas Bisbrouck, Mathieu Bauchy, John D. Vienna
Summary: The study on QSPR analysis using MD simulations provides insights into the composition-property relationships of glasses and complex materials. The F-net structural descriptor shows the best correlation with the initial dissolution rates of glasses. For glasses with incongruent dissolution, modifying glass compositions to account for the preferential release of modifier cations is necessary for achieving optimal correlations.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2021)
Article
Materials Science, Ceramics
Joelle T. Reiser, Benjamin Parruzot, Stephane Gin, Jeffrey F. Bonnett, Courtney S. Smoljan, Lorraine M. Seymour, Joseph Ryan, John D. Vienna
Summary: Understanding the alteration mechanisms of borosilicate glasses in aqueous media is crucial for nuclear waste performance assessments. The addition of aluminum to glass compositions is typically used to reduce alteration, but the relationship is found to be nonlinear. Research on the effects of aluminum and silicon ratios on glass durability showed that increasing aluminum to silicon ratios led to decreased overall alteration, while changes in the (aluminum plus sodium) to silicon ratio had minimal impact except at high levels, where complete alteration occurred within a short time frame.
INTERNATIONAL JOURNAL OF APPLIED GLASS SCIENCE
(2022)
Review
Chemistry, Multidisciplinary
Gerald S. Frankel, John D. Vienna, Jie Lian, Xiaolei Guo, Stephane Gin, Seong H. Kim, Jincheng Du, Joseph Ryan, Jianwei Wang, Wolfgang Windl, Christopher D. Taylor, John R. Scully
Summary: This article discusses the material science issues related to long-term performance assessment and design of materials with improved performance against aqueous corrosion in deep geological repositories for high-level radioactive waste. It covers advances in the field of materials corrosion for glass, crystalline ceramics, and metals, and provides recommendations for future research directions.
Article
Chemistry, Physical
Hicham Jabraoui, Thibault Charpentier, Stephane Gin, Jean-Marc Delaye, Rodolphe Pollet
Summary: Reactivity and leaching at the calcium sodium borosilicate (CNBS)-water interface were studied through molecular dynamics simulation. The behaviors of Ca2+ and Na+ cations were compared, revealing that Na+ ions can be released in solution while Ca2+ ions cannot leave the surface. The energetically favorable vacancy structure for Na+ ions promotes their release, while the structure for Ca2+ ions inhibits their release.
JOURNAL OF CHEMICAL PHYSICS
(2022)
Article
Materials Science, Ceramics
Huseyin Kaya, Stephane Gin, Bryan D. Vogt, Seong H. Kim
Summary: This study investigates the aqueous corrosion mechanism of a model boroaluminosilicate glass at ground water relevant pHs. The results reveal that alteration layers formed under different pH conditions exhibit similar porous network structures, but with differences in bond lengths and bond angles in the glass network. Furthermore, the relative abundance of hydrous species within the alteration layer appears to be pH-dependent.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2022)
Article
Materials Science, Ceramics
Xiaonan Lu, Lu Deng, Stephane Gin, Benjamin Parruzot, Joelle T. Reiser, Joseph Ryan, John D. Vienna, Jincheng Du
Summary: Predicting the chemical durability of glass materials is crucial for various applications. This study investigates the prediction of glass dissolution rates through molecular dynamics simulations and provides insights on improving existing models.
JOURNAL OF THE AMERICAN CERAMIC SOCIETY
(2023)
Article
Materials Science, Ceramics
Amreen Jan, Jean-Marc Delaye, Huseyin Kaya, Seong H. Kim, Anamul Haq Mir, Thibault Charpentier, Frederic Angeli, Stephane Gin
Summary: In this study, the behavior of pristine and preirradiated glasses under aqueous corrosion conditions was investigated using experimental and simulation methods. The results showed that preirradiation significantly increased the initial dissolution rate and the depth of the alteration layer. Furthermore, radiation-induced structural changes and enhanced water diffusion were observed.
INTERNATIONAL JOURNAL OF APPLIED GLASS SCIENCE
(2023)
Article
Materials Science, Ceramics
Kamalesh Damodaran, Stephane Gin, Jean-Vincent De Montgolfier, Christophe Jegou, Jean-Marc Delaye
Summary: This study found that the simultaneous presence of B and Ca in the solution can significantly slow down the alteration of glass, while splitting B and Ca into different solutions does not provide similar protection. In addition, experiments showed that the diffusion of water is not dramatically affected by the retention of B and Ca in the passivating gels, and slow diffusion and high retention of B were observed only in gels developed in basic pH conditions.
JOURNAL OF NON-CRYSTALLINE SOLIDS
(2022)
Article
Materials Science, Multidisciplinary
Kamalesh Damodaran, Stephane Gin, Sathya Naranayasamy, Jean-Marc Delaye
Summary: The research finds that the chemical durability of borosilicate glass used for nuclear waste confinement is nonlinearly related to its composition, making it difficult to predict the rate of glass dissolution. The study focuses on the impact of aluminum, an important oxide in these materials. Through experiments conducted at 90 degrees Celsius and pH 9, the initial and residual glass dissolution rates were examined. The results indicate that glasses with lower aluminum content dissolve initially faster but quickly achieve a lower residual rate due to the formation of a more passivating gel. However, higher aluminum content gel will eventually achieve passivation with a slower reorganization. The strengthening effect of aluminum on the hydrolysis of the Si-O bond will result in more stable gels, suggesting that a slightly higher aluminum content in the gel can improve the durability of nuclear high-level waste glass under geological disposal conditions.
NPJ MATERIALS DEGRADATION
(2023)
Article
Materials Science, Multidisciplinary
S. Gin, C. Jegou, L. Sessegolo, N. Bisbrouck, A. Jan, M. Tribet, J. M. Delaye, F. Angeli
Summary: The study found that swift heavy ion irradiation can lead to increased alteration of glass under Si saturation conditions. This is due to the increased hydrolysis speed of Si-O-B bonds and a less passivating alteration layer.
NPJ MATERIALS DEGRADATION
(2022)
Article
Materials Science, Multidisciplinary
N. Bisbrouck, M. Micoulaut, J. M. Delaye, S. Gin, F. Angeli
Summary: This study investigates the initial dissolution rate of multicomponent glasses to evaluate the impact of increasing magnesium content on the alteration process and compare the behavior of calcium- and magnesium-bearing glasses. The results suggest that substituting calcium for magnesium reduces the initial dissolution rate, while increasing magnesium content leads to an increased dissolution rate. The analysis with topological constraint theory indicates that the magnesium environment is better defined than calcium or sodium, possibly acting as an intermediate species.
NPJ MATERIALS DEGRADATION
(2022)
Article
Materials Science, Multidisciplinary
Chandi Mohanty, Xiaolei Guo, Huseyin Kaya, Stephane Gin, Kun Yang, Zelong Zhang, Seong H. Kim, Jie Lian, Jianwei Wang, Gerald S. Frankel
Summary: The interactive corrosion between stainless steel 316 and International Simple Glass has been studied, and it was found that the corrosion of SS is closely related to the dissolution of nearby glass. The corrosion rate of SS was suppressed in the solution saturated with silica species.
NPJ MATERIALS DEGRADATION
(2022)
Article
Materials Science, Multidisciplinary
Benjamin Cagnon, Damien Daval, Martiane Cabie, Damien Lemarchand, Stephane Gin
Summary: The dissolution of amorphous and crystalline oligoclase under acidic conditions was investigated. It was found that the altered layer on the amorphous samples was mainly formed by leaching, while a combination of both interfacial precipitation and leaching explained the layers formed on the crystalline samples. The amorphous oligoclase showed a faster alteration rate compared to the crystalline counterpart, which was attributed to its more open structure.
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)
