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Neutron transport = theory, modeling, and computations /

紀錄類型:	書目-語言資料,印刷品 : Monograph/item
正題名/作者:	Neutron transport/ by Ramadan M. Kuridan.
其他題名:	theory, modeling, and computations /
作者:	Kuridan, Ramadan M.
出版者:	Cham :Springer Nature Switzerland : : 2023.,
面頁冊數:	xii, 282 p. :ill. (some col.), digital ; : 24 cm.;
Contained By:	Springer Nature eBook
標題:	Computational Mathematics and Numerical Analysis. -
電子資源:	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:

669338
Computational Mathematics and Numerical Analysis.

LC Class. No.: QC793.5.N4628

Dewey Class. No.: 539.7

Neutron transport = theory, modeling, and computations /
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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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