Thermo-Hydraulics of Nuclear Reactors

Christopher Earls Brennen

doi:10.1017/CBO9781316494264

This book provides a concise and up-to-date summary of the essential thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation. Beginning with the basic nuclear physics, it leads through technical and quantitative analyses to descriptions of both the normal operation of the various modern nuclear reactor designs and the analyses of the possible departures from normal operation. It then describes both the postulated accident scenarios and summaries of the causes for the three major nuclear power generation accidents, Three Mile Island, Chernobyl and Fukushima, as well as the major improvements to reactor safety that grew out of those analyses and accidents.

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Thermo-Hydraulics of Nuclear Reactors

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Contents

Frontmatter
pp i-iv

Contents
pp v-viii

Preface
pp ix-x

Mathematical Nomenclature
pp xi-xvi

1 - Introduction
pp 1-4

2 - Basic Nuclear Power Generation
pp 5-24

3 - Core Neutronics
pp 25-55

4 - Some Reactor Designs
pp 56-77

5 - Core Heat Transfer
pp 78-89

6 - Multiphase Flow
pp 90-126

7 - Reactor Multiphase Flows and Accidents
pp 127-150

Index
pp 151-155

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