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Adaptive matrix formation (AMF) method of space–time multigroup reactor kinetics equations in multidimensional model

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Outgoing claims: the papers this work cites, builds on, or argues with.

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Matrix Iterative Analysis
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The physical theory of neutron chain reactors
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Progress in nodal methods for the solution of the neutron diffusion and transport equations
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Acceleration of the outer iterations of the space-dependent neutron kinetics equations solution
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Solution of two-dimensional space–time multigroup reactor kinetics equations by generalized Padé and cut-product approximations
inferredcites →https://doi.org/10.1016/s0306-4549(96)00036-9openalex-snapshot
Application of preconditioned transpose-free quasi-minimal residual method for two-group reactor kinetics
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The Elements of Nuclear Reactor Theory
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Space-Time Nuclear Reactor Kinetics
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The Elements of Nuclear Reactor Theory
inferredcites →https://doi.org/10.13182/nse38-8openalex-snapshot
Comparison of Alternating-Direction Time-Differencing Methods with Other Implicit Methods for the Solution of the Neutron Group-Diffusion Equations
inferredcites →https://doi.org/10.13182/nse41-431openalex-snapshot
Alternating Direction Methods for the Reactor Kinetics Equations
inferredcites →https://doi.org/10.13182/nse59-289openalex-snapshot
Multidimensional Space-Time Nuclear-Reactor Kinetics Studies—Part I: Theoretical
inferredcites →https://doi.org/10.13182/nse71-a19671openalex-snapshot
Application of Alternating-Direction Implicit Methods to the Space-Dependent Kinetics Equations
inferredcites →https://doi.org/10.13182/nse73-a23278openalex-snapshot
Finite Element Methods for Reactor Analysis
inferredcites →https://doi.org/10.13182/nse73-a26594openalex-snapshot
Solution of the Space-Dependent Reactor Kinetics Equations in Three Dimensions
inferredcites →https://doi.org/10.13182/nse77-a27061openalex-snapshot
Coarse-Mesh Flux-Expansion Method for the Analysis of Space-Time Effects in Large Light Water Reactor Cores
inferredcites →https://doi.org/10.13182/nse77-a27386openalex-snapshot
High-Order Schemes for Neutron Kinetics Calculations, Based on a Local Polynomial Approximation
inferredcites →https://doi.org/10.13182/nse77-a27389openalex-snapshot
Current Trends in Methods for Neutron Diffusion Calculations
inferredcites →https://doi.org/10.13182/nse78-a27300openalex-snapshot
Computational Methods in Engineering and Science
inferredcites →https://doi.org/10.13182/nse85-7openalex-snapshot
A Resolution of the Stiffness Problem of Reactor Kinetics
inferredcites →https://doi.org/10.13182/nse94-a21481openalex-snapshot
An Investigation of the Temporal Subdomain Method for Solving the Finite Element Formulation of the Space-Time Reactor Kinetics Equations
inferredcites →https://doi.org/10.2172/10102801openalex-snapshot
A quasi-static polynomial nodal method for nuclear reactor analysis
inferredcites →https://doi.org/10.2172/10102858openalex-snapshot
A transient, quadratic nodal method for triangular-Z geometry
inferredcites →https://doi.org/10.2307/2003862openalex-snapshot
Matrix Iterative Analysis

What points at this work

Incoming claims: where this work appears in other papers’ reference lists and arguments.

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Efficient Rational Approximations of Multi-Energy Groupspoint Kinetics Model for Multi-Dimensional Homogenous
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On the Mono-Energetic Neutron Space Kinetics Equation in Cartesian Geometry: An Analytic Solution by a Spectral Method
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Mono-Energetic Neutron Space-Kinetics in Full Cylinder Symmetry: Simulating Power Decrease
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Analytical technique of multi-energy groups point kinetics model for multidimensional homogeneous reactors
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Generalization of the analytical solution of neutron point kinetics equations with time-dependent external source
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On an extended variable separation method approach to the neutron space kinetics equations with two energy groups and six groups of delayed neutron precursors
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Optimizing Multi-Energy Group Point-Reactor Kinetics Using Rational Approximations and Concise Analytical Formula
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Criticality calculations in a nuclear reactor by using the Lyapunov exponent method
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Solving the multigroup integro-differential equation of the neutron diffusion kinetics in 3D-Cartesian geometry
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Efficient computational system for transient neutron diffusion model via finite difference and theta methods
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Non symmetric alternating direction explicit method applied to the calculation of ADS transients
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On an analytical formulation for the mono-energetic neutron space-kinetic equation in full cylinder symmetry
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Numerical simulation of the nuclear reactors kinetics behavior using method of lines based on the GDQ method
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Probability distribution for neutron density of two energy group point kinetics system
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On an analytical solution for the two energy group neutron space-kinetic equation in heterogeneous cylindrical geometry
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Introduction to the non-orthogonal gradient-based finite volume method for three-dimensional neutron diffusion calculations with application to the rectangular reactor core configurations
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Fractional two energy groups matrix representation for nuclear reactor dynamics with an external source
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Semi wavelet-based improved quasi static method for the analysis of PHWR transients
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An efficient exponential representation for solving the two-energy group point telegraph kinetics model
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Spectrum analysis of two energy groups space-dependent neutron telegraph kinetics model
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Hermite methods for multi-energy group neutron kinetics model via quasi-static approach and piecewise functions
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A positivity-preserving finite volume scheme for multi-group neutron diffusion kinetics equations with delayed neutrons
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Forward sensitivity analysis procedure (FSAP) with improved quasi static method for the estimation of dynamic uncertainty in reactor transients
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Development of a neutron space–time kinetics solver with improved quasi-static method based on OpenFOAM
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A new formula of neutron multiplication during startup of PWR
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Stiffness treatment of differential equations for the point reactor dynamic systems
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A novel mathematical model for two-energy groups of the point kinetics reactor dynamics
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The modified exponential time differencing method with IQS model for the neutronic analysis of PHWR transients
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A study on the solution of the spatial kinetics equations in the neutron diffusion theory
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Theta Method Applied to Two-Energy Groups Point Kinetics Equations
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Rational approximations for multi-energy group stiff fractional point kinetics equations
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Computationally efficient modeling of stiff multi-energy groups fractional reactor dynamics using sophisticated rational techniques
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Generalization of the Analytical Exponential Model for Homogeneous Reactor Kinetics Equations
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OPTIMALISASI DISTRIBUSI PRODUK BEBICARE MENGGUNAKAN METODE SAVING MATRIX PADA CV. ANUGERAH JAYA MANDIRI
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Küresel Bir Nükleer Reaktör İçin Ana ve Alternatif Bükülmedeki Değişimlerin Kritik Yarıçapa Etkisi
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Penentuan pola distribusi optimal menggunakan metode saving matrix untuk meningkatkan fleksibilitas pemesanan
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