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Neutron transport = theory, modeling...

Kuridan, Ramadan M.

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Neutron transport = theory, modeling, and computations /

Record Type:	Electronic resources : Monograph/item
Title/Author:	Neutron transport/ by Ramadan M. Kuridan.
Reminder of title:	theory, modeling, and computations /
Author:	Kuridan, Ramadan M.
Published:	Cham :Springer Nature Switzerland : : 2023.,
Description:	xii, 282 p. :ill. (some col.), digital ;24 cm.
[NT 15003449]:	Neutron Transport - The Neutron Transport Equation -- Neutron Diffusion - The Finite Difference Solution of The Neutron Diffusion Equation -- Spherical Harmonics - The PN Method -- The Adjoint Transport Equation - The Equation of Neutron Importance -- Perturbation Theory -- The Method of Discrete Ordinates The SN Method.
Contained By:	Springer Nature eBook
Subject:	Neutron transport theory. -
Online resource:	https://doi.org/10.1007/978-3-031-26932-5
ISBN:	9783031269325

Neutron transport = theory, modeling, and computations /
Kuridan, Ramadan M.

Neutron transporttheory, modeling, and computations /[electronic resource] :by Ramadan M. Kuridan. - Cham :Springer Nature Switzerland :2023. - xii, 282 p. :ill. (some col.), digital ;24 cm. - Graduate texts in physics,1868-4521. - Graduate texts in physics..

Neutron Transport - The Neutron Transport Equation -- Neutron Diffusion - The Finite Difference Solution of The Neutron Diffusion Equation -- Spherical Harmonics - The PN Method -- The Adjoint Transport Equation - The Equation of Neutron Importance -- Perturbation Theory -- The Method of Discrete Ordinates The SN Method.

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.

ISBN: 9783031269325

Standard No.: 10.1007/978-3-031-26932-5doiSubjects--Topical Terms:

2192311
Neutron transport theory.

LC Class. No.: QC793.5.N4628

Dewey Class. No.: 539.7

Neutron transport = theory, modeling, and computations /
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260 $a Cham : $b Springer Nature Switzerland : $b Imprint: Springer, $c 2023.
300 $a xii, 282 p. : $b ill. (some col.), digital ; $c 24 cm.
490 1 $a Graduate texts in physics, $x 1868-4521
505 0 $a Neutron Transport - The Neutron Transport Equation -- Neutron Diffusion - The Finite Difference Solution of The Neutron Diffusion Equation -- Spherical Harmonics - The PN Method -- The Adjoint Transport Equation - The Equation of Neutron Importance -- Perturbation Theory -- The Method of Discrete Ordinates The SN Method.
520 $a 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.
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