Lewis | Fundamentals of Nuclear Reactor Physics | Buch | 978-0-12-370631-7 | www.sack.de

Buch, Englisch, 312 Seiten, Format (B × H): 192 mm x 259 mm, Gewicht: 803 g

Lewis

Fundamentals of Nuclear Reactor Physics


Erscheinungsjahr 2008
ISBN: 978-0-12-370631-7
Verlag: Elsevier Science Publishing Co Inc

Buch, Englisch, 312 Seiten, Format (B × H): 192 mm x 259 mm, Gewicht: 803 g

ISBN: 978-0-12-370631-7
Verlag: Elsevier Science Publishing Co Inc


Fundamentals of Nuclear Reactor Physics 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. It provides 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.

It provides in-depth discussion of neutron reactions, including neutron kinetics and the neutron energy spectrum, as well as neutron spatial distribution. It includes ample worked-out examples and over 100 end-of-chapter problems.

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.

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Zielgruppe


Junior and Senior Undergraduate engineering students in mechanical, nuclear, and materials engineering , Junior and Senior Undergraduate students in physics, Graduate Students in other engineering disciplines in need of an introductory text, including those in Electrical engineering and Environmental and Health and Safety engineering, Professional Engineers in Mechanical, Nuclear and Materials Engineering, Managers and Technicians in the power-generation industries, Administrators charged with regulatory and safety issues affecting the nuclear power industry


Autoren/Hrsg.


Weitere Infos & Material


1. Nuclear Reactions
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
Appendices
A. Useful Mathematics
B. Bessel's Equation and Functions
C. Derivation of Neutron Diffusion Properties
D. Fuel Element Heat Transfer
E. Nuclear Data


By Elmer E Lewis, Ph.D., Northwestern University Dept. Of Mechanical Engineering Robert R. McCormick School of Eng. & Applied Science Evanston, IL



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