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Gao, Yipeng; Wang, Yunzhi; Zhang, Yongfeng
Idaho National Laboratory (INL), Idaho Falls, ID (United States). Funding organisation: USDOE National Nuclear Security Administration (NNSA) (United States)2019
Idaho National Laboratory (INL), Idaho Falls, ID (United States). Funding organisation: USDOE National Nuclear Security Administration (NNSA) (United States)2019
AbstractAbstract
[en] The generation and motion of crystalline defects during plastic deformation are critical processes that determine the mechanical properties of a crystal. The types of defect generated are not only related to the symmetry of a crystal but also associated with the symmetry-breaking process during deformation. Proposed here is a new mathematical framework to capture the intrinsic coupling between crystal symmetry and deformation-induced symmetry breaking. Using a combination of group theory and graph theory, a general approach is demonstrated for the systematic determination of the types of crystalline defect induced by plastic deformation, through the construction of a crystal deformation group and a deformation pathway graph. The types of defect generated in the deformation of a face-centered cubic crystal are analyzed through the deformation pathway graph and compared with experimental observations.
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OSTIID--1617920; SC0001258; AC07-05ID14517; Available from https://www.osti.gov/biblio/1617920; DOE Accepted Manuscript full text, or the publishers Best Available Version will be available free of charge after the embargo period; Country of input: United States
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Journal Article
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IUCrJ; ISSN 2052-2525;
; v. 6(1); p. 96-104

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Zhang, Yongfeng
Idaho National Laboratory (INL), Idaho Falls, ID (United States). Funding organisation: USDOE Office of Nuclear Energy - NE (United States)2016
Idaho National Laboratory (INL), Idaho Falls, ID (United States). Funding organisation: USDOE Office of Nuclear Energy - NE (United States)2016
AbstractAbstract
[en] U3Si2 and FeCrAl have been proposed as fuel and cladding concepts, respectively, for accident tolerance fuels with higher tolerance to accident scenarios compared to UO2. However, a lot of key physics and material properties regarding their in-pile performance are yet to be explored. To accelerate the understanding and reduce the cost of experimental studies, multiscale modeling and simulation are used to develop physics-based materials models to assist engineering scale fuel performance modeling. In this report, the lower-length-scale efforts in method and material model development supported by the Accident Tolerance Fuel (ATF) high-impact-problem (HIP) under the NEAMS program are summarized. Significant progresses have been made regarding interatomic potential, phase field models for phase decomposition and gas bubble formation, and thermal conductivity for U3Si2 fuel, and precipitation in FeCrAl cladding. The accomplishments are very useful by providing atomistic and mesoscale tools, improving the current understanding, and delivering engineering scale models for these two ATF concepts.
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1 Sep 2016; vp; OSTIID--1389929; AC07-05ID14517; Available from https://inldigitallibrary.inl.gov/sites/sti/sti/7406472.pdf; PURL: http://www.osti.gov/servlets/purl/1389929/
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Report
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Zhang, Yongfeng; Millett, Paul C.; Tonks, Michael; Biner, Bulent
Idaho National Laboratory (United States). Funding organisation: US Department of Energy (United States)2012
Idaho National Laboratory (United States). Funding organisation: US Department of Energy (United States)2012
AbstractAbstract
[en] This work presents a mechanism of deformation-twin-induced grain boundary failure, and demonstrates the mechanism using molecular dynamics simulations. Deformation twinning is observed as the dominant mechanism during tensile deformation of columnar nanocrystalline body-centered cubic Mo. As a twin approaches a grain boundary, local stress concentration develops due to the incompatible plastic deformations in the two neighboring grains. The magnitude of the stress concentration increases as the twin widens, leading to grain boundary cracking by nucleation and coalescence of microcracks/voids.
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INL/JOU--11-23092; AC07-05ID14517
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Journal Article
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Gao, Yipeng; Zhang, Yongfeng; Schwen, Daniel; Jiang, Chao; Gan, Jian
Idaho National Laboratory (INL), Idaho Falls, ID (United States). Funding organisation: USDOE (United States); USDOE Office of Science - SC (United States), Basic Energy Sciences (BES) (SC-22). Materials Sciences & Engineering Division2019
Idaho National Laboratory (INL), Idaho Falls, ID (United States). Funding organisation: USDOE (United States); USDOE Office of Science - SC (United States), Basic Energy Sciences (BES) (SC-22). Materials Sciences & Engineering Division2019
AbstractAbstract
[en] Ordering and self-organization are critical in determining the dynamics of reaction-diffusion systems. Here we show a unique pattern formation mechanism, dictated by the coupling of thermodynamic instability and kinetic anisotropy. Intrinsically different from the physical origin of Turing instability and patterning, the ordered patterns we obtained are caused by the interplay of the instability from uphill diffusion, the symmetry breaking from anisotropic diffusion, and the reactions. To understand the formation of the void/gas bubble superlattices in crystals under irradiation, we establish a general theoretical framework to predict the symmetry selection of superlattice structures associated with anisotropic diffusion. Through analytical study and phase field simulations, we found that the symmetry of a superlattice is determined by the coupling of diffusion anisotropy and the reaction rate, which indicates a new type of bifurcation phenomenon. Our discovery suggests a means for designing target experiments to tailor different microstructural patterns.
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OSTIID--1619677; AC07-05ID14517; Available from https://www.osti.gov/biblio/1619677; DOE Accepted Manuscript full text, or the publishers Best Available Version will be available free of charge after the embargo period; arXiv:1903.09045; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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Scientific Reports; ISSN 2045-2322;
; v. 9(1); vp

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AbstractAbstract
[en] In the first part of this study, the stability of Cu precipitates, up to 2 nm in diameter, in Fe-1at%Cu-1at%Ni-1at%Mn system was evaluated within the framework of phase-field modeling by utilizing a thermodynamic database. The implanted precipitates either in isolated or in clustered arrangements, were unstable and dissolved into the matrix. The dissolution rate decreases with increasing precipitate size; however, it is strongly influenced by the spatial arrangements of the implants and the overall alloy content. In the second part, the precipitation/segregation behavior at a circular dislocation, and square prismatic loops was parametrically studied. While precipitates formed at the dislocation loop, a significant segregation of Cu was observed at prismatic loops with either vacancy or interstitial character. Although, the both types of prismatic loops provide the spatial evolution of the stress-fields with the same absolute magnitude, the vacancy loops appears to be stronger sinks and their sink strength increases with decreasing loop size. The results clearly show the necessity of inclusion of the underlying lattice defects in the microstructure modeling of materials under the irradiation environments.
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S0022-3115(15)30307-X; Available from http://dx.doi.org/10.1016/j.jnucmat.2015.10.062; Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Bai, Xian-Ming; Zhang, Yongfeng; Tonks, Michael R.
Structural Materials for Innovative Nuclear Systems (SMINS-3) - Workshop Proceedings, Idaho National Laboratory, Idaho Falls, United States, 7-10 October 20132015
Structural Materials for Innovative Nuclear Systems (SMINS-3) - Workshop Proceedings, Idaho National Laboratory, Idaho Falls, United States, 7-10 October 20132015
AbstractAbstract
[en] Zirconium alloys are the major fuel cladding materials in current reactors. The water-side corrosion is a significant degradation mechanism of these alloys. During corrosion, the transport of oxidizing species in zirconium dioxide (ZrO2) determines the corrosion kinetics. Previously, it has been argued that the outward diffusion of cations is important for forming protective oxides. In this work, the migration of Zr defects in tetragonal ZrO2 is studied with temperature accelerated dynamics and molecular dynamics simulations. The results show that Zr interstitials have anisotropic diffusion and migrate preferentially along the [001] or c direction in tetragonal ZrO2. The compressive stresses can increase the Zr interstitial migration barrier significantly. The migration of Zr interstitials at a grain boundary is much slower than in a bulk oxide. The implications of these atomistic simulation results in the Zr corrosion are discussed. (authors)
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Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Nuclear Science Committee - NSC, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France); 287 p; 2015; p. 260-267; SMINS-3: Structural Materials for Innovative Nuclear Systems; Idaho Falls (United States); 7-10 Oct 2013; 19 refs.
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AbstractAbstract
[en] We analyze the accumulation of fission gas on grain boundaries in a polycrystalline microstructure with a distribution of grain sizes. The diffusion equation is solved throughout the microstructure to evolve the gas concentration in space and time. Grain boundaries are treated as infinite sinks for the gas concentration, and we monitor the cumulative gas inventory on each grain boundary throughout time. We consider two important cases: first, a uniform initial distribution of gas concentration without gas production (correlating with post-irradiation annealing), and second, a constant gas production rate with no initial gas concentration (correlating with in-reactor conditions). The results show that a single-grain-size model, such as the Booth model, over predicts the gas accumulation on grain boundaries compared with a polycrystal with a grain size distribution. Also, a considerable degree of scatter, or variability, exists in the grain boundary gas accumulation when comparing all of the grain boundaries in the microstructure
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S0022-3115(13)00811-8; Available from http://dx.doi.org/10.1016/j.jnucmat.2013.05.065; Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Zhang, Liangzhe; Tonks, Michael R.; Millett, Paul C.; Zhang, Yongfeng; Chockalingam, Karthikeyan; Biner, Bulent
Idaho National Laboratory (United States). Funding organisation: DOE - NE (United States)2012
Idaho National Laboratory (United States). Funding organisation: DOE - NE (United States)2012
AbstractAbstract
[en] Pore migration in a temperature gradient (Soret effect) is investigated by a phase-field model coupled with a heat transfer calculation. Pore migration is observed towards the high temperature domain with velocities that agree with analytical solution. Due to the low thermal conductivity of the pores, the temperature gradient across individual pores is increased, which in turn, accelerates the pore migration. In particular, for pores filled with xenon and helium, the pore velocities are increased by a factor of 2.2 and 2.1, respectively. A quantitative equation is then derived to predict the influence of the low thermal conductivity of pores.
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INL/JOU--11-23842; AC07-05ID14517
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Journal Article
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Computational Materials Science; ISSN 0927-0256;
; v. 56; p. 161-165

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AbstractAbstract
[en] A parametric study has been performed that quantifies the effective change in grain boundary Kapitza resistance due to the presence of intergranular bubbles. The steady-state heat conduction equation was solved in three-dimensional space using INL’s MOOSE finite element software, with which spacial mesh adaptivity was used to resolve interfacial widths down to several nanometers while investigating bubble sizes up to a micrometer. Three critical parameters were systematically varied: the intergranular bubble radius, the fractional grain boundary bubble coverage, and the Kapitza resistance of the intact grain boundary. Using the simulation results, a mathematical model dependent on each of these parameters was developed to describe the effective Kapitza resistance. Furthermore, we illustrate how this model can be implemented in a fuel performance code to predict the temperature profile of a cylindrical fuel pellet
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S0022-3115(13)00445-5; Available from http://dx.doi.org/10.1016/j.jnucmat.2013.02.039; Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Beeler, Benjamin; Zhang, Yongfeng; Gao, Yipeng, E-mail: benjamin.beeler@inl.gov2018
AbstractAbstract
[en] A monolithic fuel design based on a U-Mo alloy has been selected as the fuel type for conversion of the United States High-Performance Research Reactors (HPRRs). A 2015 post-irradiation examination (PIE) report showed accelerated swelling in U-10Mo fuels at fission densities much lower than previously observed. This PIE report showed a large amount of compositional banding, or regions of low Mo content adjacent to regions of high Mo content, with low Mo content typically along grain boundaries. Lower Mo content can lead to phase decomposition from the gamma U-Mo body-centered cubic phase to the alpha U phase as well as an earlier onset of recrystallization. Thus, the phenomenon of Mo depletion at grain boundaries is an important factor in the accelerated swelling behavior of U-Mo fuel. However, the physical origin of Mo depletion at grain boundaries is still unclear. In this work, molecular dynamics simulations have been performed to calculate the grain boundary and surface energies of body-centered cubic (bcc) U, bcc Mo and alloys of U-Mo from 600 K to 1200 K. It is observed that the lower grain boundary energy of bcc U, compared to bcc Mo, provides the driving force for Mo depletion at grain boundaries. This driving force diminishes with increasing temperature, but is not eliminated. This information can be utilized as inputs to higher length scale modeling methodologies and provide specification guidance to fabricators.
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S0022311518301454; Available from http://dx.doi.org/10.1016/j.jnucmat.2018.05.007; Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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ACTINIDE ALLOYS, ALLOYS, CALCULATION METHODS, CRYSTAL LATTICES, CRYSTAL STRUCTURE, CUBIC LATTICES, ELEMENTS, ENERGY, FLUIDS, FREE ENERGY, GASES, MICROSTRUCTURE, MOLYBDENUM ALLOYS, NONMETALS, PHYSICAL PROPERTIES, RARE GASES, REACTORS, RESEARCH AND TEST REACTORS, SURFACE PROPERTIES, THERMODYNAMIC PROPERTIES, THREE-DIMENSIONAL LATTICES, TRANSITION ELEMENT ALLOYS, URANIUM ALLOYS
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