Reactor design basics
Author(s)
Bibliographic Information
Reactor design basics
(Nuclear reactor engineering / Samuel Glasstone & Alexander Sesonske, v. 1)
Chapman & Hall, 1994
4th ed
Available at 9 libraries
  Aomori
  Iwate
  Miyagi
  Akita
  Yamagata
  Fukushima
  Ibaraki
  Tochigi
  Gunma
  Saitama
  Chiba
  Tokyo
  Kanagawa
  Niigata
  Toyama
  Ishikawa
  Fukui
  Yamanashi
  Nagano
  Gifu
  Shizuoka
  Aichi
  Mie
  Shiga
  Kyoto
  Osaka
  Hyogo
  Nara
  Wakayama
  Tottori
  Shimane
  Okayama
  Hiroshima
  Yamaguchi
  Tokushima
  Kagawa
  Ehime
  Kochi
  Fukuoka
  Saga
  Nagasaki
  Kumamoto
  Oita
  Miyazaki
  Kagoshima
  Okinawa
  Korea
  China
  Thailand
  United Kingdom
  Germany
  Switzerland
  France
  Belgium
  Netherlands
  Sweden
  Norway
  United States of America
Note
Includes bibliographical references and index
Description and Table of Contents
Description
This reference guide combines a coverage of nuclear engineering principles with practical descriptions of their application in the design and operation of nuclear power plants. It should be of interest to nuclear engineers, mechanical engineers and industrial engineers.
Table of Contents
- Chapter 1: Energy from nuclear fission: Introduction
- Nuclear energy fundamentals
- Nuclear fission
- Nuclear fission reactors
- Chapter 2: Nuclear reactions and radiations: Introduction
- Radioactivity
- Interaction of alfha and beta particles with matter
- Interaction of gamma rays with matter
- Interaction of neutrons with matter
- Cross sections for neutron reactions
- Variation of cross sections with neutron energy
- The fission process
- Chapter 3: Neutron transport behavior: Neutron transport concepts
- Neutron diffusion theory
- Diffusion in multiplying systems
- The slowing down of neutrons
- Slowing down in infinite media
- Spatial distribution of slowed-down neutrons
- Critical equations based on diffusion theory
- Criticality measurements
- Chapter 4: Nuclear design basics: Introduction
- Multigroup diffusion theory
- Fuel depletion calculations
- The neutron transport equation and its approximation
- Chapter 5: Nuclear reactor kinetics and control: Introduction
- Reactor kinetics
- Fission-product poisoning
- Effect of temperature on reactivity
- Reactor stability analysis
- General features of reactor control
- Reactivity control instrumentation
- Reactor operations
- Chapter 6: Radiation protection and shielding: Introduction
- Health physics activities
- Radiation units
- Biological effects of radiation
- Radiation protection standards
- Radiation shielding principles
- Radiation attenuation calculations
- Reactor shield analysis
- Heating in shields
- Chapter 7: Reactor materials: Introduction
- Mechanical properties of materials
- Stress analysis
- Radiation effects in materials
- Corrosion of metals
- Structural and cladding materials
- Moderator and reflector materials
- Fuel materials
- Appendix
- Index.
by "Nielsen BookData"