| Titre : |
Fundamentals of nuclear reactor physics |
| Type de document : |
texte imprimé |
| Auteurs : |
E. E. Lewis, Auteur |
| Editeur : |
New York : Academic press |
| Année de publication : |
2008 |
| Importance : |
XI, 293 p. |
| Présentation : |
ill. |
| Format : |
27 cm |
| ISBN/ISSN/EAN : |
978-0-12-370631-7 |
| Note générale : |
Bibliogr. - Index
|
| Langues : |
Anglais (eng) |
| Mots-clés : |
Physique nucléaire -- Réacteurs nucléaires |
| Index. décimale : |
621.039.51 Théorie et expérimentation fondamentale des réacteurs. Physique des réacteurs |
| Résumé : |
This new streamlined text offers a one-semester treatment of the essentials of how the fission nuclear reactor works, the various approaches to the design of reactors, and their safe and efficient operation. The book includes numerous worked-out examples and end-of-chapter questions to help reinforce the knowledge presented.
This textbook offers an engineering-oriented introduction to nuclear physics, with a particular focus on how those physics are put to work in the service of generating nuclear-based power, particularly the importance of neutron reactions and neutron behavior. Engineering students will find this applications-oriented approach, with many worked-out examples, more accessible and more meaningful as they aspire to become future nuclear engineers.
· A clear, general overview of atomic physics from the standpoint of reactor functionality and design, including the sequence of fission reactions and their energy release
· In-depth discussion of neutron reactions, including neutron kinetics and the neutron energy spectrum, as well as neutron spatial distribution
· Ample worked-out examples and over 100 end-of-chapter problems. |
| Note de contenu : |
Summary :
1. Nuclear Réactions
2. Neutron Interactions
3. Neutron Distributions in Energy
4. The Power Reactor Core
5. Reactor Kinetics
6. Spatial Diffusion of Neutrons
7. Neutron Distributions in Reactors
8. Energy Transport
9. Reactivity Feedback
10. Long Term Core Behavior
A. Useful Mathematics
B. Bessel's Equation and Functions
C. Derivation of Neutron Diffusion Properties
D. Fuel Element Heat Transfer
E. Nuclear Data |
Fundamentals of nuclear reactor physics [texte imprimé] / E. E. Lewis, Auteur . - New York : Academic press, 2008 . - XI, 293 p. : ill. ; 27 cm. ISBN : 978-0-12-370631-7 Bibliogr. - Index
Langues : Anglais ( eng)
| Mots-clés : |
Physique nucléaire -- Réacteurs nucléaires |
| Index. décimale : |
621.039.51 Théorie et expérimentation fondamentale des réacteurs. Physique des réacteurs |
| Résumé : |
This new streamlined text offers a one-semester treatment of the essentials of how the fission nuclear reactor works, the various approaches to the design of reactors, and their safe and efficient operation. The book includes numerous worked-out examples and end-of-chapter questions to help reinforce the knowledge presented.
This textbook offers an engineering-oriented introduction to nuclear physics, with a particular focus on how those physics are put to work in the service of generating nuclear-based power, particularly the importance of neutron reactions and neutron behavior. Engineering students will find this applications-oriented approach, with many worked-out examples, more accessible and more meaningful as they aspire to become future nuclear engineers.
· A clear, general overview of atomic physics from the standpoint of reactor functionality and design, including the sequence of fission reactions and their energy release
· In-depth discussion of neutron reactions, including neutron kinetics and the neutron energy spectrum, as well as neutron spatial distribution
· Ample worked-out examples and over 100 end-of-chapter problems. |
| Note de contenu : |
Summary :
1. Nuclear Réactions
2. Neutron Interactions
3. Neutron Distributions in Energy
4. The Power Reactor Core
5. Reactor Kinetics
6. Spatial Diffusion of Neutrons
7. Neutron Distributions in Reactors
8. Energy Transport
9. Reactivity Feedback
10. Long Term Core Behavior
A. Useful Mathematics
B. Bessel's Equation and Functions
C. Derivation of Neutron Diffusion Properties
D. Fuel Element Heat Transfer
E. Nuclear Data |
|  |
621 Ingenierie mecanique en general. Technologie nucleaire. Ingenierie electrique. Machinerie
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