Works matching DE "NEUTRON diffusion"
Results: 54
Optimization of Core Regions and Fuel Fractions for Better Power Peaking Factor of 150, 450 and 1,000 MWth Molten Salt Reactor.
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- Trends in Sciences, 2023, v. 20, n. 12, p. 1, doi. 10.48048/tis.2023.6937
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Evaluation of The IAEA 2D PWR Benchmark Problem Using TRIVAC and OpenMOC Codes.
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- Annals of the University of Craiova, Physics, 2018, v. 28, p. 24
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Solving Multi-Group Reflected Spherical Reactor System of Equations Using the Homotopy Perturbation Method.
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- Mathematics (2227-7390), 2022, v. 10, n. 10, p. 1784, doi. 10.3390/math10101784
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Solving a Novel System of Time-Dependent Nuclear Reactor Equations of Fractional Order.
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- Symmetry (20738994), 2024, v. 16, n. 7, p. 831, doi. 10.3390/sym16070831
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Electric-field influence on the neutron diffuse scattering near the ferroelectric transition of Sr 0.61 Ba 0.39 Nb 2 O 6.
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- Phase Transitions, 2016, v. 89, n. 7/8, p. 808, doi. 10.1080/01411594.2016.1186275
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Gapless neutron superfluidity in the crust of the accreting neutron stars KS 1731−260 and MXB 1659−29.
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- European Physical Journal A -- Hadrons & Nuclei, 2024, v. 60, n. 5, p. 1, doi. 10.1140/epja/s10050-024-01329-z
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Modeling Neutron Emissions in High Energy Atmospheric Phenomena.
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- Journal of Geophysical Research. Atmospheres, 2018, v. 123, n. 22, p. 12,726, doi. 10.1029/2018JD028962
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The effect of neutron irradiation on the diffusion of Ar in alkali feldspar.
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- Geophysical Research Abstracts, 2019, v. 21, p. 1
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Solving the discretised neutron diffusion equations using neural networks.
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- International Journal for Numerical Methods in Engineering, 2023, v. 124, n. 21, p. 4659, doi. 10.1002/nme.7321
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An autoencoder‐based reduced‐order model for eigenvalue problems with application to neutron diffusion.
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- International Journal for Numerical Methods in Engineering, 2021, v. 122, n. 15, p. 3780, doi. 10.1002/nme.6681
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Parametric uncertainty quantification using proper generalized decomposition applied to neutron diffusion.
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- International Journal for Numerical Methods in Engineering, 2019, v. 119, n. 9, p. 899, doi. 10.1002/nme.6077
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Preconditioning the solution of the time-dependent neutron diffusion equation by recycling Krylov subspaces.
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- International Journal of Computer Mathematics, 2014, v. 91, n. 1, p. 42, doi. 10.1080/00207160.2013.771181
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Research on the Effect of Fracture Angle on Neutron Logging Results of Shale Gas Reservoirs.
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- Energies (19961073), 2024, v. 17, n. 13, p. 3342, doi. 10.3390/en17133342
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An Efficient and Robust ILU(k) Preconditioner for Steady-State Neutron Diffusion Problem Based on MOOSE.
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- Energies (19961073), 2024, v. 17, n. 6, p. 1499, doi. 10.3390/en17061499
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Investigation and Validation of Unstructured Mesh Methodologies for Modeling Experimental Reactors.
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- Energies (19961073), 2022, v. 15, n. 4, p. 1512, doi. 10.3390/en15041512
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Reduced-Order Modelling with Domain Decomposition Applied to Multi-Group Neutron Transport.
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- Energies (19961073), 2021, v. 14, n. 5, p. 1369, doi. 10.3390/en14051369
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Reduced-Order Modelling Applied to the Multigroup Neutron Diffusion Equation Using a Nonlinear Interpolation Method for Control-Rod Movement.
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- Energies (19961073), 2021, v. 14, n. 5, p. 1350, doi. 10.3390/en14051350
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Comprehensive Second-Order Adjoint Sensitivity Analysis Methodology (2nd-ASAM) Applied to a Subcritical Experimental Reactor Physics Benchmark: I. Effects of Imprecisely Known Microscopic Total and Capture Cross Sections.
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- Energies (19961073), 2019, v. 12, n. 21, p. 4219, doi. 10.3390/en12214219
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A neutron diffuse scattering study of PbZrO<sub>3</sub> and Zr-rich PbZr<sub>1- x</sub>Ti <sub>x</sub>O<sub>3</sub>.
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- Journal of Applied Crystallography, 2015, v. 48, n. 6, p. 1637, doi. 10.1107/S1600576715017069
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A Novel Scheme of the ARA Transform for Solving Systems of Partial Fractional Differential Equations.
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- Fractal & Fractional, 2023, v. 7, n. 4, p. 306, doi. 10.3390/fractalfract7040306
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Using Laplace Residual Power Series Method in Solving Coupled Fractional Neutron Diffusion Equations with Delayed Neutrons System.
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- Fractal & Fractional, 2023, v. 7, n. 3, p. 219, doi. 10.3390/fractalfract7030219
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A Consistent One-Dimensional Multigroup Diffusion Model for Molten Salt Reactor Neutronics Calculations.
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- Journal of Nuclear Engineering (JNE), 2023, v. 4, n. 4, p. 654, doi. 10.3390/jne4040041
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Neural Network Based Deep Learning Method for Multi-Dimensional Neutron Diffusion Problems with Novel Treatment to Boundary.
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- Journal of Nuclear Engineering (JNE), 2021, v. 2, n. 4, p. 533, doi. 10.3390/jne2040036
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Modelling and control for eliminating flux oscillations in generation IV high temperature gas cooled reactor.
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- Electronics Letters (Wiley-Blackwell), 2016, v. 52, n. 3, p. 190, doi. 10.1049/el.2015.1749
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Strategies of Preconditioner Updates for Sequences of Linear Systems Associated with the Neutron Diffusion.
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- Computational & Mathematical Methods, 2022, p. 1, doi. 10.1155/2022/3884836
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Development and Verification of a Spatial Dynamics Code RESTA‐3D for Light Water Reactors.
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- International Journal of Energy Research, 2025, v. 2025, p. 1, doi. 10.1155/er/5377974
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A Meshless Method Based on Symmetric RBF Collocation for Neutron Diffusion Problems.
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- Acta Physica Polonica: A, 2019, v. 135, n. 4, p. 661, doi. 10.12693/APhysPolA.135.661
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Analysis of NEA-NSC PWR Uncontrolled Control Rod Withdrawal at Zero Power Benchmark Cases with NODAL3 Code.
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- Science & Technology of Nuclear Installations, 2017, p. 1, doi. 10.1155/2017/5151890
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Evaluation of relevant information for optimal reflector modeling through data assimilation procedures.
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- EPJ Nuclear Sciences & Technologies, 2015, v. 1, p. 1, doi. 10.1051/epjn/e2015-50022-3
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Uncertainty Analysis on Neutron Diffusion Equation Using Fuzzy α-cut Approach.
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- International Journal of Computer Science & Applications, 2014, v. 11, n. 2, p. 105
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Resolution of the Generalized Eigenvalue Problem in the Neutron Diffusion Equation Discretized by the Finite Volume Method.
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- Abstract & Applied Analysis, 2014, p. 1, doi. 10.1155/2014/913043
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Radiokrypton and radioxenon diffusion in silicate and sodium chloride media.
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- Journal of Radioanalytical & Nuclear Chemistry, 2022, v. 331, n. 12, p. 5161, doi. 10.1007/s10967-022-08533-5
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THE GREEN FUNCTION FOR TIME INDEPENDENT MULTI-VELOCITY TRANSPORT EQUATION.
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- Reports of Enlarged Sessions of Seminar of I. Vekua Institute of Applied Mathematics, 2016, n. 30, p. 110
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Addendum: Shqair, M., et al. Analytical Solution for Multi-Energy Groups of Neutron Diffusion Equations by a Residual Power Series Method. Mathematics 2019, 7, 633.
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- Mathematics (2227-7390), 2019, v. 7, n. 11, p. 1061, doi. 10.3390/math7111061
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Analytical Solution for Multi-Energy Groups of Neutron Diffusion Equations by a Residual Power Series Method.
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- Mathematics (2227-7390), 2019, v. 7, n. 7, p. 633, doi. 10.3390/math7070633
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Diffusion coefficients and constraints on hadronic inhomogeneities in the early universe.
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- European Physical Journal C -- Particles & Fields, 2019, v. 79, n. 5, p. N.PAG, doi. 10.1140/epjc/s10052-019-6938-6
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The Verification of Coupled Neutronics Thermal-Hydraulics Code NODAL3 in the PWR Rod Ejection Benchmark.
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- Science & Technology of Nuclear Installations, 2014, p. 1, doi. 10.1155/2014/845832
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Generalized Correction Algorithm for the Finite-Difference Diffusion Equations in Askew-Takeda Method.
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- Physics of Atomic Nuclei, 2018, v. 81, n. 8, p. 1170, doi. 10.1134/S1063778818080045
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Numerical solution of uncertain neutron diffusion equation for imprecisely defined homogeneous triangular bare reactor.
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- Sādhanā: Academy Proceedings in Engineering Sciences, 2015, v. 40, n. 7, p. 2095, doi. 10.1007/s12046-015-0433-z
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A posteriori error estimates for mixed finite element discretizations of the Neutron Diffusion equations.
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- ESAIM: Mathematical Modelling & Numerical Analysis (ESAIM: M2AN), 2023, v. 57, n. 1, p. 1, doi. 10.1051/m2an/2022078
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Investigation of the use of momentum and Galerkin weighting functions in high-order Nodal expansion method to solve the neutron diffusion equation.
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- Radiation Physics & Engineering, 2022, v. 3, n. 3, p. 39, doi. 10.22034/RPE.2022.337683.1078
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Second order average current nodal expansion method for time-dependent neutron diffusion simulation.
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- Radiation Physics & Engineering, 2021, v. 2, n. 3, p. 9, doi. 10.22034/rpe.2021.300458.1037
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基于氧化腐蚀行为的铅铋堆燃料组件 多物理耦合特性研究.
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- Atomic Energy Science & Technology, 2024, v. 58, n. 10, p. 2139, doi. 10.7538/yzk.2023.youxian.0810
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基于降阶模型的中子扩散特征值问题的 不确定性分析研究.
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- Atomic Energy Science & Technology, 2023, v. 57, n. 8, p. 1575, doi. 10.7538/yzk.2022.youxian.0832
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CorTAF2.0核热耦合及杂质沉积模块开发及初步应用.
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- Atomic Energy Science & Technology, 2023, v. 57, p. 45, doi. 10.7538/yzk.2023.youxian.0096
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基于COMSOL Multiphysics的中子扩散问题 求解以及气冷微堆应用分析.
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- Atomic Energy Science & Technology, 2023, v. 57, n. 3, p. 565, doi. 10.7538/yzk.2022.youxian.0354
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A fully coupled two‐level Schwarz preconditioner based on smoothed aggregation for the transient multigroup neutron diffusion equations.
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- Numerical Linear Algebra with Applications, 2018, v. 25, n. 3, p. 1, doi. 10.1002/nla.2162
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NUMERICAL ANALYSIS OF THE SELF-SUSTAINING TRAVELING WAVE OF NUCLEAR FISSION PROPAGATED BY EPITHERMAL NEUTRONS IN URANIUM DICARBIDE MEDIUM.
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- Nuclear Physics & Atomic Energy, 2024, v. 25, n. 4, p. 357, doi. 10.15407/jnpae2024.04.357
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NEUTRON STUDIES OF DIFFUSION PROCESSES NEAR A SINGULAR POINT IN A DILUTE AQUEOUS SOLUTION OF ETHANOL.
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- Nuclear Physics & Atomic Energy, 2023, v. 24, n. 3, p. 283, doi. 10.15407/jnpae2023.03.283
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ADVANTAGE OF A DYNAMICAL (B/Gd) NEUTRON BEAM CANCER THERAPY OVER A STATIONARY THERAPY.
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- Nuclear Physics & Atomic Energy, 2020, v. 21, n. 1, p. 101, doi. 10.15407/jnpae2020.01.101
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