Article
Physics, Multidisciplinary
A. Durif, M. Richou, Y. Corre, C. Delommez, J-P Gunn
Summary: One of the missions of the WEST tokamak is to test the plasma facing components made with tungsten in a realistic tokamak environment. This paper presents the results of numerical simulations on the damage process of the leading edge of the components. The results provide insights into the thermal gradients, softening fraction gradient, and stress and strain distributions in tungsten under different heat flux conditions.
Article
Multidisciplinary Sciences
O. El Atwani, H. T. Vo, M. A. Tunes, C. Lee, A. Alvarado, N. Krienke, J. D. Poplawsky, A. A. Kohnert, J. Gigax, W. -Y Chen, M. Li, Y. Q. Wang, J. S. Wrobel, D. Nguyen-Manh, J. K. S. Baldwin, O. U. Tukac, E. Aydogan, S. Fensin, E. Martinez
Summary: The authors develop an irradiation resistant, thermally stable, and strong refractory high entropy alloy (RHEA) for nuclear application through a combination of simulation and experiments. This research is of great significance in the quest for new materials that can withstand severe irradiation and mechanical extremes for advanced applications.
NATURE COMMUNICATIONS
(2023)
Article
Materials Science, Multidisciplinary
T. Muroga, Y. Hatano, D. Clark, Y. Katoh
Summary: The Joint Projects under the Japan-USA Fusion Cooperation Program have been conducting research on neutron radiation effects on fusion reactor materials for over 40 years. The projects have focused on fundamental radiation effects, correlation of irradiation, and the development of candidate materials, contributing significantly to the advancement of fusion technology.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Nuclear Science & Technology
G. Pintsuk, M. Missirlian, G-N Luo, Q. Li, W. Wang, D. Guilhem, J. Bucalossi
Summary: The qualification of suppliers for actively cooled tungsten targets for the lower divertor of WEST involved cyclic high heat flux tests on small-scale mock-ups based on ITER design, resulting in successful performance and subsequent qualification through hardness tests and microstructural analyses.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Nuclear Science & Technology
A. Grosjean, Y. Corre, J. Gaspar, J. P. Gunn, S. Carpentier, X. Courtois, R. Dejarnac, E. Delmas, G. De Temmerman, M. Diez, L. Dubus, L. Dupont, F. Escourbiac, M. Firdaouss, J. Gerardin, M. Houry, R. Pitts, C. Pocheau, E. Tsitrone
Summary: Fourteen ITER-like plasma-facing units (PFUs) made of bulk tungsten were installed in the WEST tokamak divertor, with five misaligned PFUs exposing their poloidal leading edges to the plasma heat flux. The parallel heat flux measured on the outer strike point indicated a real temperature of about 1000 degrees C on the leading edges. A significant discrepancy between modeling and measurement was observed in the toroidal temperature profile, along with evidence of surface state modification caused by plasma exposure on the component.
NUCLEAR MATERIALS AND ENERGY
(2021)
Article
Materials Science, Multidisciplinary
M. Klimenkov, M. Duerrschnabel, U. Jaentsch, P. Lied, M. Rieth, H. C. Schneider, D. Terentyev, W. Van Renterghem
Summary: Pure W material was neutron irradiated at temperatures ranging from 600°C to 1200°C, resulting in the formation of voids, dislocation loops, and W-Re-Os containing precipitates. The microstructure analysis revealed the detailed structure of these defects, including the size and distribution of voids, precipitates, and loops. Additionally, chemical and structural analysis showed that the defects were surrounded by a solid solution cloud enriched with Re and Os, and nanoscale chemical analysis identified differences in Re/Os segregation at and near the defects.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Multidisciplinary Sciences
Max Boleininger, Daniel R. Mason, Andrea E. Sand, Sergei L. Dudarev
Summary: Below the onset of vacancy migration, metals exposed to energetic ions develop fluctuating steady-state microstructures. The statistical properties of these microstructures in the high exposure limit depend on the energy and mass of the incident ions. A model is developed to describe the microstructure of an ion-irradiated metal under athermal conditions, where internal stress fluctuations dominate the structural evolution kinetics. The model predicts that low energy ions produce more damage than high energy ions at comparable levels of radiation exposure.
SCIENTIFIC REPORTS
(2023)
Article
Materials Science, Multidisciplinary
F. Granberg, J. Byggmastar, K. Nordlund
Summary: Tungsten is chosen as the plasma-facing wall material in fusion reactors due to its high density and melting point. Research shows that the choice of interatomic potential significantly affects the evolution of defects, while the structure and stability of defect configurations can be validated using a quantum-accurate Gaussian approximation potential.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Alan Xu, Tao Wei, Ken Short, Tim Palmer, Mihail Ionescu, Dhriti Bhattacharyya, George D. W. Smith, David E. J. Armstrong
Summary: Micro-tensile testing was used to study the response of pure tungsten and two tungsten alloys to helium ion irradiation. The results showed an increase in strength and a loss of ductility in the irradiated samples compared to the unirradiated ones. The micro-tensile results were comparable to nanoindentation measurements in terms of irradiation hardening among the different materials.
JOURNAL OF MATERIALS SCIENCE
(2023)
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
Nuclear Science & Technology
Hyoung Chan Kim, Eunnam Bang, Kyung-Min Kim, Yeonju Oh, Heung Nam Han, Jieun Choi, Suk-Ho Hong
Summary: This study investigates the material properties of tungsten mono-blocks subjected to high heat flux tests. Various parameters including hardness, microstructure, and surface state were measured to evaluate the integrity of the fabricated mono-blocks, and the impacts of the high heat flux test on the tungsten armors were analyzed. The correlation between microstructure and hardness profile was studied to understand the effects of the mockup performance under HHF test.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Optics
Yue Zhou, Dawei Bi, Songlin Wang, Longsheng Wu, Yi Huang, Enxia Zhang, Daniel M. Fleetwood, Aimin Wu
Summary: In this study, the radiation responses of silicon photonic passive devices in silicon-on-insulator technology were investigated. High-energy neutron and Co-60 gamma-ray irradiation caused blue shifts in the wavelengths of micro-ring resonators and Mach-Zehnder interferometers. The devices with SiO2 upper cladding layer exhibited strong tolerance to irradiation.
Article
Nuclear Science & Technology
Kuo Zhang, Jeong-Ha You
Summary: Within the EUROfusion framework, the thermal stress and fracture analysis of the DEMO-divertor design with a copper alloy heat sink were carried out to evaluate the structural integrity of the tungsten armor of the plasma facing component. Finite element method (FEM) and extended finite element method (XFEM) were used to assess the influence of mesh and tungsten plasticity, fracture strength, and toughness on crack initiation and propagation.
FUSION ENGINEERING AND DESIGN
(2022)
Article
Materials Science, Multidisciplinary
J. Wu, F. Granberg
Summary: Tungsten is chosen as the material for demanding parts in fusion test reactors and power plants. Material degradation due to irradiation necessitates component replacement. Understanding how defects are formed is crucial for predicting replacement needs. Low energy simulations and Frenkel-pair insertion method are compared to investigate the potential of the latter in accelerating cascade simulations. Results show similarities qualitatively, but differences quantitatively, particularly at higher energies.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Materials Science, Multidisciplinary
F. Granberg, D. R. Mason, J. Byggmaestar
Summary: Tungsten is the preferred material for plasma-facing components in fusion reactors. Computer simulations are necessary to understand defect accumulation at an atomistic level. This article investigates accelerated methods for simulating defect evolution and compares them to computationally heavy cumulative simulations. It is found that the acceleration technique chosen can significantly affect defect evolution, but applying cascade annealing can lead to similar results regardless of the initial technique used.
COMPUTATIONAL MATERIALS SCIENCE
(2023)
Article
Materials Science, Multidisciplinary
Shuhei Nogami, Akira Hasegawa, Makoto Fukuda, Michael Rieth, Jens Reiser, Gerald Pintsuk
Summary: This paper discusses the drawbacks of tungsten as a plasma facing material in fusion reactors and the efforts to improve its mechanical properties through collaborative research and development. Methods such as grain refining, K-doping, dispersion strengthening, and alloying with Re are explored to enhance the performance of tungsten materials. However, there are concerns regarding the intrinsic issues of materials alloyed with Re under high dose neutron irradiation.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Eiichi Wakai, Shigeru Takaya, Yoshinori Matsui, Yuji Nagae, Shoichi Kato, Tomoaki Suzudo, Masataka Yamaguchi, Kazumi Aoto, Shuhei Nogami, Akira Hasegawa, Hiroaki Abe, Koichi Sato, Taku Ishida, Shunsuke Makimura, Patrick G. Hurh, Kavin Ammigan, David J. Senor, Andrew M. Casella, Danny J. Edwards
Summary: This study focuses on the mechanical property changes and microstructural development induced by displacement damage and helium production in materials irradiated in heavy irradiation environments. It was found that helium atoms strongly influence the creep lifetime of irradiated austenitic stainless steel, and that the reduction ratio of creep rupture time does not decrease linearly with helium production. The research also discusses high radiation resistance materials for high-energy accelerator driven target systems.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Chemistry, Physical
Hanns Gietl, Takaaki Koyanagi, Xunxiang Hu, Makoto Fukuda, Akira Hasegawa, Yutai Katoh
Summary: This study provides experimental evidence of radiation-enhanced recrystallization in tungsten and undoped tungsten-rhenium alloys under fusion-relevant environments. It is found that potassium or lanthanum doping in tungsten alloys improves resistance to radiation-enhanced grain growth. The study also highlights the importance of considering radiation-enhanced recrystallization in the design and application of tungsten plasma-facing components in future nuclear fusion reactors.
JOURNAL OF ALLOYS AND COMPOUNDS
(2022)
Article
Materials Science, Multidisciplinary
Koichi Sato, Ryuta Kasada, Atsushi Kiyohara, Masashi Hirabaru, Kenichi Nakano, Kiyohiro Yabuuchi, Masahiko Hatakeyama, Qiu Xu
Summary: The effects of hydrogen atoms on the hardness of unirradiated, ion-irradiated, and electron-irradiated polycrystalline tungsten samples were investigated using nanoindentation tests. The study found that the hardness of unirradiated and electron-irradiated tungsten samples did not change upon hydrogen charging, while the hardness of ion-irradiated tungsten samples increased. The hydrogen atoms were mainly trapped at dislocation loops, and the hardening was mainly caused by an increase in the obstacle strength of vacancy clusters containing hydrogen atoms.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Materials Science, Multidisciplinary
Ken-ichi Fukumoto, Kohei Umehara, Kiyohiro Yabuuchi
Summary: A series of in-situ TEM observations were conducted on ion-irradiated stainless steel during tensile deformation. The study revealed that dislocations in the material were pinned and depinned at the defects, and Frank loops and black dots were found to strongly interact with dislocations.
Article
Nuclear Science & Technology
Takeshi Miyazawa, Kento Matsui, Akira Hasegawa
Summary: This study investigates the effects of microstructural anisotropy and helium implantation on the tensile properties of powder metallurgy processed tungsten (PM-W) materials. The results show that microstructural anisotropy and crack formation occur at low temperatures, and helium implantation significantly affects crack propagation.
NUCLEAR MATERIALS AND ENERGY
(2022)
Article
Nuclear Science & Technology
Takeshi Miyazawa, Haruka Saito, Yoshimitsu Hishinuma, Takuya Nagasaka, Takeo Muroga, Jingjie Shen, Yasuki Okuno, Hao Yu, Ryuta Kasada, Akira Hasegawa
Summary: The effect of Ta content on the Charpy impact properties of four V-Ta-4Cr-4Ti quaternary alloys was investigated. It was found that both the upper shelf energy and the ductile-brittle transition temperature increased with increasing Ta content. The addition of 3 wt.% Ta resulted in solid solution strengthening without any degradation of the Charpy impact properties. Further characterization of precipitates, thermal aging, and creep tests are needed to determine the optimum Ta content.
NUCLEAR MATERIALS AND ENERGY
(2022)
Article
Nuclear Science & Technology
Kouichi Tougou, Maoto Fukui, Ken-ichi Fukumoto, Ryoya Ishigami, Kiyohiro Yabuuchi
Summary: The irradiation hardening factor of cavities with a diameter of 2 nm in tungsten was investigated to be 0.53, with about 11% of the cross-slip behavior attributed to the dynamic interaction between screw dislocations and cavities. The fraction of cross-slip behavior in tungsten was found to be smaller compared to other BCC structure materials.
NUCLEAR MATERIALS AND ENERGY
(2022)
Article
Materials Science, Multidisciplinary
Peng Song, Kiyohiro Yabuuchi, Philippe Spaetig
Summary: FeCrAl(Zr)-ODS ferritic steels were studied to understand their radiation hardening behavior. Irradiation-induced hardening increased with increasing displacement damage, and the addition of Zr reduced the ion-irradiation hardening. The relationship between the plastically deformed zone size and the density of geometrically necessary dislocations was determined.
Article
Materials Science, Multidisciplinary
Shuhei Nogami, Itsuki Ozawa, Daisuke Asami, Naoya Matsuta, Seiji Nakabayashi, Siegfried Baumgaertner, Philipp Lied, Kiyohiro Yabuuchi, Takeshi Miyazawa, Yuta Kikuchi, Marius Wirtz, Michael Rieth, Akira Hasegawa
Summary: The addition of tantalum to tungsten-tantalum alloys improves their mechanical properties, resistance against recrystallization, and resistance to high heat flux exposure. This makes them a promising material for fusion reactor applications.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Materials Science, Multidisciplinary
Kiyohiro Yabuuchi, Tomoaki Suzudo
Summary: Irradiation defects in reactor materials lead to degradation of mechanical properties. This study focuses on the relationship between dislocations and defects, specifically investigating the interaction between an edge dislocation and different faceted void geometrical combinations in pure iron. The results reveal the differences in obstacle strength and cutting process between spherical voids and faceted voids, with the highest critical shear stress observed at different regions depending on the faceted void configuration type. The cutting process is influenced by the faceted plane, with the {1101 plane of the faceted void requiring the highest amount of energy to cut the atomic binding.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Materials Science, Multidisciplinary
Takuya Yamamoto, Yuan Wu, Kiyohiro Yabuuchi, Jack Haley, Kenta Yoshida, Akihiko Kimura, G. Robert Odette
Summary: The microstructural evolutions of two variants of the F82H 8 wt%Cr tempered martensitic steel under dual ion irradiations have been investigated. The study focuses on the effects of displacements per atom (dpa) and the helium/dpa ratio (He/dpa) on cavity evolution and void swelling. The analysis suggests that local microstructural variations contribute to the observed scatter in the data, and the highest void swelling data provides the most appropriate estimate of swelling for fusion neutron irradiation conditions. The dose dependence of void swelling can be described by an incubation dpa and a post-incubation swelling rate, which both decrease with increasing He/dpa.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Materials Science, Multidisciplinary
Takeshi Miyazawa, Yuta Kikuchi, Masami Ando, Ju-Hyeon Yu, Kiyohiro Yabuuchi, Takashi Nozawa, Hiroyasu Tanigawa, Shuhei Nogami, Akira Hasegawa
Summary: This study explores the effects of alloying elements (Re and Ta) on the microstructural evolution of recrystallized tungsten (W) under proton and self-ion irradiations. It is found that the addition of Re and Ta suppresses the formation of voids in W. The presence of Re inhibits the mobility of small dislocation loops and SIA clusters, while Ta inhibits the mobility of SIA clusters. In self-ion irradiation, solute Re suppresses the raft formation and void formation. The main reason for the irradiation hardening of W-3%Re is the presence of voids and dislocation loops.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Materials Science, Multidisciplinary
Akihiko Kimura, Wei Sang, Wentuo Han, Kiyohiro Yabuuchi, Zongxi Xin, Junhua Luan, Peng Dou
Summary: The age-hardening behavior of oxide dispersion strengthened (ODS) ferritic steels with different Cr and Al contents was studied through Vickers hardness measurement and tensile tests after ageing at 475 degrees C for up to 900 hours. Atom probe tomography (APT) was used to investigate the evolution of nanometer-scale structure and chemistry. The results revealed that the age-hardening mechanism in ODS steels involves alpha-alpha' phase separation and/or the precipitation of (Al, Ti)-enriched f1 phases. The concentration and volume fraction of alpha' phase increased significantly with increasing Cr content, while the chemical compositions and volume fraction of f1 phases remained relatively constant during ageing.
JOURNAL OF NUCLEAR MATERIALS
(2023)
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)
