4.7 Article

Ab initio study of interstitial cluster interaction with Re, Os, and Ta in W

Journal

JOURNAL OF NUCLEAR MATERIALS
Volume 484, Issue -, Pages 30-41

Publisher

ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2016.11.002

Keywords

Fusion; Tungsten; Interstitial cluster; Structure; Stability; Dissociation; Solute; Binding energy; Density functional theory; Finite-size scaling; Semicore states; Transmutation; Diffusion

Funding

  1. U. S. Department of Energy Office of Fusion Energy Sciences [DE-AC06-76RL0-1830]

Ask authors/readers for more resources

The stability of tungsten self-interstitial atom (SIA) clusters is studied using first-principles methods. Clusters from one to seven SIAs are systematically explored from 1264 unique configurations. Finite-size effect of the simulation cell is corrected based on the scaling of formation energy versus inverse volume cell. Furthermore, the accuracy of the calculations is improved by treating the 5p semicore states as valence states. ConfigUrations of the three most stable clusters in each cluster size n are presented, which consist of parallel 1111] dumbbells. The evolution of these clusters leading to small dislocation loops is discussed. The binding energy of size-n clusters is analyzed relative to an n ->(n-1) + 1 dissociation and is shown to increase with size. Extrapolation for n> 7 is presented using a dislocation loop model. In addition, the interaction of these clusters with a substitutional Re, Os, or Ta solute is explored by replacing one of the dumbbells with the solute. Re and Os strongly attract these clusters, but Ta strongly repels. The strongest interaction is found when the solute is located on the periphery of the cluster rather than in the middle. The magnitude of this interaction decreases with cluster size. Empirical fits to describe the trend of the solute binding energy are presented. Published by Elsevier B.V.

Authors

I am an author on this paper
Click your name to claim this paper and add it to your profile.

Reviews

Primary Rating

4.7
Not enough ratings

Secondary Ratings

Novelty
-
Significance
-
Scientific rigor
-
Rate this paper

Recommended

Article Materials Science, Ceramics

Role of interfaces in damage process of irradiated lithium aluminate nanocrystals

Wahyu Setyawan, David J. Senor, Ram Devanathan

JOURNAL OF THE AMERICAN CERAMIC SOCIETY (2019)

Article Chemistry, Physical

Sequestration of Radionuclides in Metal-Organic Frameworks from Density Functional Theory Calculations

Shubham Pandey, Zhilin Jia, Brian Demaske, Otega A. Ejegbavwo, Wahyu Setyawan, Charles H. Henager, Natalia Shustova, Simon R. Phillpot

JOURNAL OF PHYSICAL CHEMISTRY C (2019)

Article Materials Science, Multidisciplinary

Effect of confinement of SIA cluster diffusion by impurities on radiation defect accumulation due to 14 MeV neutrons in tungsten

Giridhar Nandipati, Wahyu Setyawan, Kenneth J. Roche, Richard J. Kurtz, Brian D. Wirth

JOURNAL OF NUCLEAR MATERIALS (2020)

Article Materials Science, Multidisciplinary

Dose rate effects on damage accumulation and void growth in self-ion irradiated tungsten

Weilin Jiang, Yuanyuan Zhu, Limin Zhang, Danny J. Edwards, Nicole R. Overman, Giridhar Nandipati, Wahyu Setyawan, Charles H. Henager, Richard J. Kurtz

Summary: This study investigated dose rate effects in self-ion irradiated mono-W and poly-W, revealing that the disordering rate in mono-W irradiated at 900 K is significantly influenced by dose rate. Voids were uniformly distributed in both mono-W and poly-W irradiated at 900 K, with a corrected diameter range of 1.5 to 3.4 nm.

JOURNAL OF NUCLEAR MATERIALS (2021)

Article Nanoscience & Nanotechnology

The effect of hot rolling on the strength and fracture toughness of 90W-7Ni3Fe tungsten heavy metal alloys

M. E. Alam, J. Wang, C. H. Henager, W. Setyawan, G. R. Odette

Summary: The effect of hot rolling on the room temperature mechanical properties of liquid-phase sintered tungsten heavy metal alloys was explored. It was found that 0% and 87% hot rolled WHAs showed higher toughness and stable crack growth, while 62% and 74% hot rolled WHAs experienced elastic fracture.

MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING (2021)

Article Physics, Condensed Matter

Effect of helium flux on near-surface helium accumulation in plasma-exposed tungsten

Giridhar Nandipati, Karl D. Hammond, Dimitrios Maroudas, Kenneth J. Roche, Richard J. Kurtz, Brian D. Wirth, Wahyu Setyawan

Summary: In this study, object kinetic Monte Carlo simulations were used to investigate the effect of helium flux on near-surface helium accumulation in plasma-facing tungsten. The simulations showed that as the flux decreases, the retention of implanted helium decreases and its depth distribution shifts deeper below the surface. Moreover, the fraction of retained helium diffusing into the bulk increases, and at a given flux, the fraction initially decreases and then starts to increase with increasing fluence. The near-surface helium accumulation spreads deeper into the material and saturates at depths between 80 and 100 nm.

JOURNAL OF PHYSICS-CONDENSED MATTER (2022)

Article Chemistry, Physical

Defect formation and bending properties in graphite under He atom implantation investigated by molecular dynamics method

X. H. Long, W. Setyawan, K. P. Tai, Y. Liu, M. S. Yu, Z. Q. Wang, N. Gao, X. L. Wang

Summary: The formation and evolution of radiation defects and their effects on the bending property of graphite under low energy helium atom implantation were studied using molecular dynamics simulations. The results provide a new understanding for the further application of graphite in nuclear reactors.

CARBON (2022)

Article Materials Science, Multidisciplinary

Helium interaction with solutes and impurities in neutron-irradiated nanostructured ferritic alloys: A first principles study

Krishna Chaitanya Pitike, Huibin Ke, Danny J. Edwards, Wahyu Setyawan

Summary: Density functional theory (DFT) calculations were used to investigate the binding between helium (He) and alloying elements in neutron irradiated nanostructured ferritic alloys (NFAs). The results showed that certain elements exhibited significant binding with interstitial and substitutional He, which could reduce He transport and promote He bubble formation in the matrix.

JOURNAL OF NUCLEAR MATERIALS (2022)

Article Materials Science, Multidisciplinary

Coupled effect of Cr and Al on interactions between a prismatic interstitial dislocation loop and an edge dislocation line in Fe-Cr-Al alloy

Miaosen Yu, Ziqiang Wang, Fei Wang, Wahyu Setyawan, Xuehao Long, Yong Liu, Limin Dong, Ning Gao, Fei Gao, Xuelin Wang

Summary: The segregation behavior of Cr and Al atoms to a prismatic dislocation loop in a Fe-Cr-Al alloy is investigated using molecular dynamics method and ab initio energy calculation. The results show that Cr can segregate to the loops, while Al atoms cannot segregate by themselves. However, the presence of segregated Cr atoms can promote Al segregation, resulting in a coupled segregation of Cr and Al. Furthermore, the pinning behavior of the dislocation loop to an edge dislocation motion can be affected by Al segregation through the coupled segregation process.

ACTA MATERIALIA (2023)

Article Materials Science, Multidisciplinary

Defect substructure energy landscape in polycrystalline Al under large deformation: insights from molecular dynamics

Nanjun Chen, Shenyang Hu, Wahyu Setyawan, Peter Sushko, Suveen N. Mathaudhu

Summary: During solid phase processing (SPP), defect substructures such as dislocation network, nanotwin, and new grain or phase can form, which has a significant impact on the stability and evolution of phase and structure. By using molecular dynamics simulations, the effect of local stresses on the formation and transformation of defect substructures in polycrystalline Al was analyzed. The study established an energy landscape for defect substructures under compress and shear stresses, showing unstable and metastable states.

JOURNAL OF MATERIALS RESEARCH AND TECHNOLOGY-JMR&T (2023)

Article Materials Science, Multidisciplinary

Diffusion-assisted growth of periodic patterns on metal surfaces

Wei Qian, Pengfei Zheng, Ning Gao, Wahyu Setyawan, Peng Chen, Xing Liu, Yong Liu, Liangting Sun, Ming Liu, Tong Che, Ran Wei, Jiming Chen

Summary: Periodic patterns formed on solid surfaces can significantly impact material properties, and understanding the underlying mechanisms is crucial for controlling pattern formation. This study observes periodic patterns induced by low-energy plasma exposures on tungsten surfaces and develops new formation mechanisms. Experimental and simulation results show that pattern formation is dominantly driven by atom diffusion accelerated by low energy and high flux exposures. The similar pattern formation has also been confirmed on molybdenum through plasma exposure experiments. Based on this mechanism, patterns with controllable shapes have been successfully prepared on tungsten surfaces by adjusting plasma exposure parameters, providing new insights into pattern formation and surface damage caused by plasma exposures on tungsten.

ACTA MATERIALIA (2023)

Article Materials Science, Multidisciplinary

Behavior and properties of helium cavities in ductile-phase-toughened tungsten irradiated with He+ ions at an elevated temperature

Weilin Jiang, Libor Kovarik, Karen Kruska, Yucheng Fu, Zhihan Hu, Lin Shao, Wahyu Setyawan

Summary: Ductile-phase toughened tungsten (DPT W) composites have been studied for their potential use in plasma-facing components in fusion power systems. The composites consist of tungsten particles embedded in a ductile NiFeW solution matrix. Irradiation of the composites with He+ ions was performed and the resulting He cavities in both tungsten and NiFeW phases were analyzed. The average cavity diameter in NiFeW was found to be approximately 2.7 times larger than that in tungsten, with a lower number density. The He atoms in the cavities in NiFeW were under-pressurized, while those in cavities in tungsten were not detectable. The relationship between the He energy-loss shift and cavity density in NiFeW was found to be similar to that observed in martensitic steel.

MATERIALIA (2023)

Article Materials Science, Multidisciplinary

Electronic structures and magnetism of Zr-, Th-, and U-based metal-organic frameworks (MOFs) by density functional theory

Shubham Pandey, Brian Demaske, Otega A. Ejegbavwo, Anna A. Berseneva, Wahyu Setyawan, Natalia Shustova, Simon R. Phillpot

COMPUTATIONAL MATERIALS SCIENCE (2020)

Article Materials Science, Multidisciplinary

H dissolution and desorption near He-V complexes in W surfaces with different orientations

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

Effect of deposition parameters on characteristics and oxidation behavior of magnetron sputtered Cr coatings

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

Automated analysis of grain morphology in TEM images using convolutional neural network with CHAC algorithm

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

Model development for oxidation and degradation behavior of accident tolerant Cr coating on Zr alloy cladding under high temperature steam atmosphere

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

Numerical and experimental development of cupronickel filler brazed joints for divertor and first wall components in DEMO fusion reactor

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

Defect-specific strength factors and superposition model for predicting strengthening of ion irradiated Fe18Cr alloy

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

Synthesis and characterization of sodium-aluminophosphate based glass-ceramics containing NZP phase for HLW immobilization

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

High temperature oxidation of cold spray Cr-coated accident tolerant zirconium-alloy cladding with Nb diffusion barrier layer

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

Irradiation creep measurement and microstructural analysis of chromium nitride-coated zirconium alloy using pressurized tubes

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

Determination of impurity distribution in IG-11/110 nuclear graphite using TOF-SIMS

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

Study of multi-pebble oxidation process in high-temperature gas-cooled reactor

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

Synthesis and characterization of super occluded LiCl-KCl in zeolite-4A as a chloride salt waste form intermediate

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

Hermeticity of SiC/SiC composite and monolithic SiC tubes irradiated under radial high-heat flux

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

Theoretical estimation of multiple hydrogen isotope content in metal layers slowly co-deposited from plasmas

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

Computational study of thermophysical properties of cerium doped UO2: Effect of oxidation states

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)