Numerical Methods in the Theory of Neutron Transport PDF Download

Author: C. Budd
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Author: Guriĭ Ivanovich Marchuk
Publisher: Harwood Academic Publishers
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 632

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Author: Liangzhi Cao
Publisher: Woodhead Publishing
ISBN: 0128182229
Category : Technology & Engineering
Languages : en
Pages : 294

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Book Description
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: Bengt G. Carlson
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 34

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Author: Bengt G. Carlson
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 54

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Author: Herbert Bishop Keller
Publisher:
ISBN:
Category : Elastic scattering
Languages : en
Pages : 48

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A procedure for the direct numerical integration of the steady-state, elastic scattering neutron transport equation is presented.

Author: Bengt G. Carlson
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 50

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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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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: Ramadan M. Kuridan
Publisher: Springer Nature
ISBN: 3031269322
Category : Science
Languages : en
Pages : 284

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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: Clarence E. Lee
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 434

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