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Author : Bengt G. Carlson
Publisher :
ISBN 13 :
Total Pages : 54 pages
Book Rating : 4.3/5 (91 download)
Download or read book Numerical Formulation and Solution of Neutron Transport Problems written by Bengt G. Carlson and published by . This book was released on 1964 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Bengt G. Carlson
Publisher :
ISBN 13 :
Total Pages : 34 pages
Book Rating : 4.3/5 (91 download)
Download or read book Numerical Solution of Transient and Steady-state Neutron Transport Problems written by Bengt G. Carlson and published by . This book was released on 1959 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Guriĭ Ivanovich Marchuk
Publisher : Harwood Academic Publishers
ISBN 13 :
Total Pages : 632 pages
Book Rating : 4.3/5 (91 download)
Download or read book Numerical Methods in the Theory of Neutron Transport written by Guriĭ Ivanovich Marchuk and published by Harwood Academic Publishers. This book was released on 1986 with total page 632 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Numerical Solution of Transient and Steady-State Neutron Transport Problems written by and published by . This book was released on 1959 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A general numerical procedure, called the discrete S/sub n/ method, for solving the neutron transport equation is described. The main topics relate to the derivation of suitable difference equations, and to the problem of solving these, while maintaining generality, accuracy, and reasonable computing speed. A few comparisons with other methods are made. (auth).
Author : B. Carlson
Publisher :
ISBN 13 :
Total Pages : 38 pages
Book Rating : 4.3/5 (91 download)
Download or read book The DSN and TDC Neutron Transport Codes written by B. Carlson and published by . This book was released on 1960 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report describes two reactor codes, one for the one-dimensional geometries (DSN) and the other for the finite cylindrical case (TDC), based on the transport difference equations and calculation methods developed in "Numerical Solutions of Transient and Steady State Neutron Transport Problems" (LA-2260). Appendices I and II, which contain the actual machine codes, have been separated from the descriptive part of the report to make it easier for the user to study the material and apply it to problems.
Author : Ramadan M. Kuridan
Publisher : Springer Nature
ISBN 13 : 3031269322
Total Pages : 284 pages
Book Rating : 4.0/5 (312 download)
Download or read book Neutron Transport written by Ramadan M. Kuridan and published by Springer Nature. This book was released on 2023-10-28 with total page 284 pages. Available in PDF, EPUB and Kindle. Book excerpt: This textbook provides a thorough explanation of the physical concepts and presents the general theory of different forms through approximations of the neutron transport processes in nuclear reactors and emphasize the numerical computing methods that lead to the prediction of neutron behavior. Detailed derivations and thorough discussions are the prominent features of this book unlike the brevity and conciseness which are the characteristic of most available textbooks on the subject where students find them difficult to follow. This conclusion has been reached from the experience gained through decades of teaching. The topics covered in this book are suitable for senior undergraduate and graduate students in the fields of nuclear engineering and physics. Other engineering and science students may find the construction and methodology of tackling problems as presented in this book appealing from which they can benefit in solving other problems numerically. The book provides access to a one dimensional, two energy group neutron diffusion program including a user manual, examples, and test problems for student practice. An option of a Matlab user interface is also available.
Author : Herbert Bishop Keller
Publisher :
ISBN 13 :
Total Pages : 48 pages
Book Rating : 4.3/5 (91 download)
Download or read book On the Numerical Integration of the Neutron Transport Equation written by Herbert Bishop Keller and published by . This book was released on 1955 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt: A procedure for the direct numerical integration of the steady-state, elastic scattering neutron transport equation is presented.
Author : Bruce Carl Wilson
Publisher :
ISBN 13 :
Total Pages : 306 pages
Book Rating : 4.:/5 (157 download)
Download or read book High Order Variational Solutions of Time-dependent Neutron Transport Problems written by Bruce Carl Wilson and published by . This book was released on 1985 with total page 306 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Jacques Tagoudjeu
Publisher : Universal-Publishers
ISBN 13 : 1599423960
Total Pages : 161 pages
Book Rating : 4.5/5 (994 download)
Download or read book New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations written by Jacques Tagoudjeu and published by Universal-Publishers. This book was released on 2011-04 with total page 161 pages. Available in PDF, EPUB and Kindle. Book excerpt: This thesis focuses on iterative methods for the treatment of the steady state neutron transport equation in slab geometry, bounded convex domain of Rn (n = 2,3) and in 1-D spherical geometry. We introduce a generic Alternate Direction Implicit (ADI)-like iterative method based on positive definite and m-accretive splitting (PAS) for linear operator equations with operators admitting such splitting. This method converges unconditionally and its SOR acceleration yields convergence results similar to those obtained in presence of finite dimensional systems with matrices possessing the Young property A. The proposed methods are illustrated by a numerical example in which an integro-differential problem of transport theory is considered. In the particular case where the positive definite part of the linear equation operator is self-adjoint, an upper bound for the contraction factor of the iterative method, which depends solely on the spectrum of the self-adjoint part is derived. As such, this method has been successfully applied to the neutron transport equation in slab and 2-D cartesian geometry and in 1-D spherical geometry. The self-adjoint and m-accretive splitting leads to a fixed point problem where the operator is a 2 by 2 matrix of operators. An infinite dimensional adaptation of minimal residual and preconditioned minimal residual algorithms using Gauss-Seidel, symmetric Gauss-Seidel and polynomial preconditioning are then applied to solve the matrix operator equation. Theoretical analysis shows that the methods converge unconditionally and upper bounds of the rate of residual decreasing which depend solely on the spectrum of the self-adjoint part of the operator are derived. The convergence of theses solvers is illustrated numerically on a sample neutron transport problem in 2-D geometry. Various test cases, including pure scattering and optically thick domains are considered.
Author : Perry A. Newman
Publisher :
ISBN 13 :
Total Pages : 122 pages
Book Rating : 4.:/5 (31 download)
Download or read book Solution of an Initial-value Problem in Linear Transport Theory written by Perry A. Newman and published by . This book was released on 1971 with total page 122 pages. Available in PDF, EPUB and Kindle. Book excerpt: The solution of an initial-value problem in linear transport theory is obtained by using the normal-mode expansion technique of Case. The problem is that of monoenergetic neutrons migrating in a thin slab surrounded by infinitely thick reflectors and the scattering is taken to be isotropic. The results obtained indicate that the reflector may give rise to a branch-cut integral term typical of a semi-infinite medium whereas the central slab may contribute a summation over discrete residue terms. Exact expressions are obtained for these discrete time eigenvalues, and numerical results showing the behavior of real time eigenvalues as a function of the material properties of the slab and reflector are presented. These eigenvalues are finite in number and may disappear into the branch cut or continuum as the material properties are varied; such disappearing eigenvalues correspond to exponentially time-decaying modes. The two largest eigenvalues can be compared with critical dimensions of slabs and spheres, and the numerical values are shown to agree with the critically results of others. In the limit of purely absorbing reflectors or a bare slab, the present solution has the same properties as have been previously reported by others who used the approach of Lehner and Wing.
Download or read book Novel Parallel Numerical Methods for Radiation & Neutron Transport written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In many of the multiphysics simulations performed at LLNL, transport calculations can take up 30 to 50% of the total run time. If Monte Carlo methods are used, the percentage can be as high as 80%. Thus, a significant core competence in the formulation, software implementation, and solution of the numerical problems arising in transport modeling is essential to Laboratory and DOE research. In this project, we worked on developing scalable solution methods for the equations that model the transport of photons and neutrons through materials. Our goal was to reduce the transport solve time in these simulations by means of more advanced numerical methods and their parallel implementations. These methods must be scalable, that is, the time to solution must remain constant as the problem size grows and additional computer resources are used. For iterative methods, scalability requires that (1) the number of iterations to reach convergence is independent of problem size, and (2) that the computational cost grows linearly with problem size. We focused on deterministic approaches to transport, building on our earlier work in which we performed a new, detailed analysis of some existing transport methods and developed new approaches. The Boltzmann equation (the underlying equation to be solved) and various solution methods have been developed over many years. Consequently, many laboratory codes are based on these methods, which are in some cases decades old. For the transport of x-rays through partially ionized plasmas in local thermodynamic equilibrium, the transport equation is coupled to nonlinear diffusion equations for the electron and ion temperatures via the highly nonlinear Planck function. We investigated the suitability of traditional-solution approaches to transport on terascale architectures and also designed new scalable algorithms; in some cases, we investigated hybrid approaches that combined both.
Author : Liangzhi Cao
Publisher : Woodhead Publishing
ISBN 13 : 0128182229
Total Pages : 294 pages
Book Rating : 4.1/5 (281 download)
Download or read book Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation written by Liangzhi Cao and published by Woodhead Publishing. This book was released on 2020-08-30 with total page 294 pages. Available in PDF, EPUB and Kindle. Book excerpt: Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation presents the latest deterministic numerical methods for neutron transport equations (NTEs) with complex geometry, which are of great demand in recent years due to the rapid development of advanced nuclear reactor concepts and high-performance computational technologies. This book covers the wellknown methods proposed and used in recent years, not only theoretical modeling but also numerical results. This book provides readers with a very thorough understanding of unstructured neutron transport calculations and enables them to develop their own computational codes. The fundamentals, numerical discretization methods, algorithms, and numerical results are discussed. Researchers and engineers from utilities and research institutes are provided with examples on how to model an advanced nuclear reactor, which they can then apply to their own research projects and lab settings. Combines the theoretical models with numerical methods and results in one complete resource Presents the latest progress on the topic in an easy-to-navigate format
Author : Tseelmaa Byambaakhuu
Publisher :
ISBN 13 :
Total Pages : 94 pages
Book Rating : 4.:/5 (13 download)
Download or read book Development of Advanced Numerical Methods for Solving Neutron Transport Problems written by Tseelmaa Byambaakhuu and published by . This book was released on 2021 with total page 94 pages. Available in PDF, EPUB and Kindle. Book excerpt: Instabilities and oscillations may occur in the solution due to sharp boundary and/or interior layers when the mesh is not fine enough around the sharp layers. Unlike the convection-diffusion problem where the singular perturbation parameter is known, the mesh transition point for hyperbolic type neutron transport problems must be determined. To address this challenge, we have analytically developed a formula to calculate this parameter. The mathematical expression calculates the boundary/interior layer thickness based on the 1D analytical solution. Numerical results for the diamond difference (DD) and discontinuous Galerkin (DG) methods are presented to improve the accuracy, stability, and efficiency of the Shishkin mesh.
Author : Roger Neil Blomquist
Publisher :
ISBN 13 :
Total Pages : 108 pages
Book Rating : 4.3/5 (91 download)
Download or read book Buckled Spherical Harmonics Solutions of Neutron Transport Problems written by Roger Neil Blomquist and published by . This book was released on 1979 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt:
![Download Variational Solutions to the Neutron Transport Equation in P[subscript N] Approximation PDF Online Free](https://books.google.com/books/content/images/frontcover/HxG5NwAACAAJ?fife=w200-h370)
Author : Mahendra Prinath Dias
Publisher :
ISBN 13 :
Total Pages : 598 pages
Book Rating : 4.:/5 (97 download)
Download or read book Variational Solutions to the Neutron Transport Equation in P[subscript N] Approximation written by Mahendra Prinath Dias and published by . This book was released on 1982 with total page 598 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Bengt G. Carlson
Publisher :
ISBN 13 :
Total Pages : 50 pages
Book Rating : 4.3/5 (91 download)
Download or read book A Method of Moments for Solving the Neutron Transport Equation written by Bengt G. Carlson and published by . This book was released on 1965 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Elmer Eugene Lewis
Publisher : Wiley-Interscience
ISBN 13 :
Total Pages : 440 pages
Book Rating : 4.3/5 (91 download)
Download or read book Computational Methods of Neutron Transport written by Elmer Eugene Lewis and published by Wiley-Interscience. This book was released on 1984 with total page 440 pages. Available in PDF, EPUB and Kindle. Book excerpt:
