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Neutronic Analysis For Nuclear Reactor Systems [Paperback]

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  • Category: Books (Technology & Engineering)
  • Author:  Zohuri, Bahman
  • Author:  Zohuri, Bahman
  • ISBN-10:  3319827065
  • ISBN-10:  3319827065
  • ISBN-13:  9783319827063
  • ISBN-13:  9783319827063
  • Publisher:  Springer
  • Publisher:  Springer
  • Binding:  Paperback
  • Binding:  Paperback
  • Pub Date:  01-Apr-2018
  • Pub Date:  01-Apr-2018
  • SKU:  3319827065-11-SPRI
  • SKU:  3319827065-11-SPRI
  • Item ID: 101358462
  • List Price: $169.99
  • Seller: ShopSpell
  • Ships in: 5 business days
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  • Delivery by: Jan 23 to Jan 25
  • Notes: Brand New Book. Order Now.
This book covers the entire spectrum of the science and technology of nuclear reactor systems, from underlying physics, to next generation system applications and beyond. Beginning with neutron physics background and modeling of transport and diffusion, this self-contained learning tool progresses step-by-step to discussions of reactor kinetics, dynamics, and stability that will be invaluable to anyone with a college-level mathematics background wishing to develop an understanding of nuclear power. From fuels and reactions to full systems and plants, the author provides a clear picture of how nuclear energy works, how it can be optimized for safety and efficiency, and why it is important to the future.
Table of Contents
About the Authors
Preface
Acknowledgment
Chapter One: Neutron Physics Background
1.0Nuclei  Sizes, Composition, and Binding Energies
1.1Decay of a Nucleus
1.2Distribution of Nuclides and Nuclear Fission/Nuclear Fusion
1.3Neutron-Nucleus Interaction
1.3.1Nuclear Reactions Rates and Neutron Cross Sections
1.3.2Effects of Temperature on Cross Section
1.3.3Nuclear Cross Section Processing Codes
1.3.4Energy Dependence of Neutron Cross Sections
1.3.5Types of Interactions
1.4Mean Free Path
1.5Nuclear Cross Section and Neutron Flux Summary
1.6Fission
1.7Fission Spectra
1.8The Nuclear Fuel
1.6.1Fertile Material
1.9Liquid Drop Model of a Nucleus
1.10Summary of Fission Process
1.11Reactor Power Calculation
1.12Relationship between Neutron Flux and Reactolĉ