5 edition of **Mathematical Topics in Neutron Transport Theory** found in the catalog.

- 299 Want to read
- 6 Currently reading

Published
**April 1998**
by World Scientific Pub Co Inc
.

Written in English

- Mathematics for scientists & engineers,
- Nuclear structure physics,
- Particle & high-energy physics,
- Engineering - Nuclear,
- Applied Mathematics,
- Science/Mathematics,
- Applied,
- Mathematical Physics,
- Mathematics,
- Neutron transport theory

The Physical Object | |
---|---|

Format | Hardcover |

Number of Pages | 344 |

ID Numbers | |

Open Library | OL9194612M |

ISBN 10 | 9810228694 |

ISBN 10 | 9789810228699 |

important mathematical methods used in neutron transport theory. The subject matter is developed from first principles, and so a previous familiarity with the theory is not strictly necessary. Neverthe-less, this book is not meant to serve as a first introduction to the subject. It is an advanced work which. Note that the two terms used here, “nuclear reactor theory” and “reactor analysis”, are used to mean nearly the same thing. The terms “reactor physics” is also sometimes used. This field addresses the neutron transport including changes of neutron characteristics. However, with the.

Jun 18, · Nuclear reactor physics is the core discipline of nuclear engineering. Nuclear reactors now account for a significant portion of the electrical power generated worldwide, and new power reactors with improved fuel cycles are being developed. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors Author: Weston M. Stacey. The integral equation describing the transport of monoenergetic, isotropically scattered neutrons in a one‐, two‐, or three‐dimensional body of arbitrary convex shape, containing distributed sources, is considered. An exact representation of the neutron density ρ(r) is obtained, involving a superposition of functions belonging to the null space of a simple differential operator. In Cited by:

Oct 15, · M. Mokhtar-Kharroubi, Mathematical Topics in Neutron Transport Theory, New Aspects, vol. 46 (World Scientific, Singapore, ) zbMATH Google Scholar M. Mokhtar-Kharroubi, L. Thevenot, On the diffusion theory of neutron transport on the savilerowandco.com by: 1. This two-part treatment introduces the general principles of the Monte Carlo method within a unified mathematical point of view, applying them to problems in neutron transport. It describes several efficiency-enhancing approaches, including the method of superposition and simulation of the adjoint equation based on reciprocity.

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Dec 01, · This book presents some recent mathematical developments about neutron transport equations. Several different topics are dealt with including regularity of velocity averages, spectral analysis of transport operators, inverse problems, nonlinear problems arising in the stochastic theory of neutron chain fissions, compactness properties of.

This book presents some recent mathematical developments about neutron transport equations. Several different topics are dealt with including regularity of velocity averages, spectral analysis of transport operators, inverse problems, nonlinear problems arising in the stochastic theory of neutron chain fissions, compactness properties of perturbed of c0-semigroups in Banach spaces with Cited by: 2.

Description: This book presents some recent mathematical developments about neutron transport equations.

Several different topics are dealt with including regularity of velocity averages, spectral analysis of transport operators, inverse problems, nonlinear problems arising in the stochastic theory of neutron chain fissions, compactness.

Mathematical Topics in Neutron Transport Theory: New Aspects - Ebook written by M. Mokhtar-Kharroubi. Read this book using Google Play Books app on your PC, android, iOS devices.

Download for offline reading, highlight, bookmark or take notes while you read Mathematical Topics in Neutron Transport Theory: New Aspects. Get this from a library. Mathematical topics in neutron transport theory: new aspects. [M Mokhtar-Kharroubi]. Neutron transport theory is the basis for development of reactor theory and reactor calculational methods.

Some of the advanced neutron transport theory methods can be easily adapted in the mathematically related fields, as for example plasma physics, astrophysics and rarified gas dynamics, and vice versa, methods used in other branches of.

Abstract. This book presents a numerical analysis of neutron transport theory. Topics considered include the kinetic reactor equation, adjoint equations, the multigroup kinetic reactor equations, the one-group kinetic equation, solution of one-group problems in the transport theory, the method of spherical harmonics, Galerkin's method, the finite-difference equations of the spherical-harmonic.

This book presents some recent mathematical developments about neutron transport equations. Several different topics are dealt with including regularity of velocity averages, spectral analysis of transport operators, inverse problems, nonlinear problems arising in the stochastic theory of Price: $ Instead, Case and Zweifel collaborated on the now classic work entitled Linear Transport Theory 2 in which the underlying mathematical theory of linear transport was presented.

The initial monograph, however, represented the coming of age of neutron transport more» theory, which had its roots in radiative transfer and kinetic theory. This book presents some recent mathematical developments about neutron transport equations.

Several different topics are dealt with including regularity of velocity averages, spectral analysis of transport operators, inverse problems, nonlinear problems arising in the stochastic theory of neutron chain fissions, compactness properties of.

The subject of this work is computational modeling of neutron trans-port relevant to economical and safe operation of nuclear facilities. The general mathematical model of neutron transport is provided by the linear Boltzmann’s transport equation and the thesis begins with its precise mathematical formulation and presentation of known con.

know anythin about nuclear fuels - and was looking for a book on Neutron transport and savilerowandco.com's web-site seems to have mixed the two books up. Computational Methods of Neutron Transport Polymers and Neutron Scattering (Oxford Series on Neutron Scattering in Condensed Matter) Simulating Enzyme Reactivity: Computational Methods in.

Buy Mathematical modeling of neutron transport: Theoretical and computational point of view on savilerowandco.com FREE SHIPPING on qualified orders. From inside the book. free path Mellin transform Monte Carlo method multi-group theory multiplying neutron distribution neutron emission neutron flux neutron transport neutron transport theory nuclei number of neutrons number of secondaries obtain orthogonality Mathematical physics Neutron transport theory Neutrons Science.

The general concept of “transport theory” refers to a physical process whereby a particle migrates through a lattice composed of scattering centers.

The first important part of this concept is that the migrating material can be considered to be a particle, in the case of interest a neutron which changes its speed of travel as its total Author: John O.

Mingle. The second part then deals with such physically and mathematically more advanced topics as neutron transport theory, neutron slowing down, resonance absorption, neutron thermalization, perturbation and variational methods, homogenization, nodal and synthesis methods, and space-time neutron dynamics.

Neutron transport is the study of the motions and interactions of neutrons with materials. Nuclear scientists and engineers often need to know where neutrons are in an apparatus, what direction they are going, and how quickly they are moving.

It is commonly used to determine the behavior of nuclear reactor cores and experimental or industrial neutron beams. If the address matches an existing account you will receive an email with instructions to reset your password. This volume presents Mathematical developments on the subject of neutron transport equations.

Several different themes are dealt with including regularity of velocity averages, spectral analysis, and inverse problems arising in the stochastic theory of neutron chain fissions.

Neutron Transport Theory and Simulation. this book will appeal to researchers and students with an interest in the progression of mathematical theory and its application to nuclear Author: Yican Wu. Neutron Transport Theory. Neutron transport theory is concerned with the transport of neutrons through various media.

As was discussed neutrons are neutral particles, therefore they travel in straight lines, deviating from their path only when they actually collide with a nucleus to be scattered into a new direction or absorbed.Existence Result for the Kinetic Neutron Transport Problem in the Presence of Delayed Neutrons Article in Transport Theory and Statistical Physics 35(3) · August with 8 Reads.A.

Schnepf, W.W. Wenzel, in Biogeochemistry of Trace Elements in the Rhizosphere, Objectives. Single root uptake models are generally based on solute transport theory, and calculate solute transport toward the root surface and uptake of solutes by the savilerowandco.comr, models on the single root scale are available that deal with root exudation and chemical non-equilibrium.