Bibliographic Information

Reactor design basics

Samuel Glasstone & Alexander Sesonske

(Nuclear reactor engineering / Samuel Glasstone & Alexander Sesonske, v. 1)

Chapman & Hall, 1994

4th ed

Available at  / 9 libraries

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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.

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Details

  • NCID
    BA23850074
  • ISBN
    • 0412985217
  • LCCN
    94016575
  • Country Code
    us
  • Title Language Code
    eng
  • Text Language Code
    eng
  • Place of Publication
    New York, N.Y. ; Tokyo
  • Pages/Volumes
    xiv, 486 p.
  • Size
    24 cm
  • Classification
  • Subject Headings
  • Parent Bibliography ID
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