Neutron Transport : Theory, Modeling, and Computations / / by Ramadan M. Kuridan
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| Autore: |
Kuridan Ramadan M
|
| Titolo: |
Neutron Transport : Theory, Modeling, and Computations / / by Ramadan M. Kuridan
|
| Pubblicazione: | Cham : , : Springer Nature Switzerland : , : Imprint : Springer, , 2023 |
| Edizione: | 1st ed. 2023. |
| Descrizione fisica: | 1 online resource (xii, 282 pages) : illustrations (some color) |
| Disciplina: | 539.7213 |
| Soggetto topico: | Nuclear physics |
| Mathematical physics | |
| Mathematics - Data processing | |
| Nuclear Physics | |
| Mathematical Methods in Physics | |
| Computational Mathematics and Numerical Analysis | |
| Nota di contenuto: | 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. |
| Sommario/riassunto: | 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. |
| Titolo autorizzato: | Neutron Transport |
| ISBN: | 3-031-26932-2 |
| Formato: | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione: | Inglese |
| Record Nr.: | 9910746992403321 |
| Lo trovi qui: | Univ. Federico II |
| Opac: | Controlla la disponibilità qui |
Serie:
Graduate Texts in Physics, . 1868-4521