Thermal Design of Nuclear Reactors - 1st Edition - ISBN: 9780080242156, 9781483145242

Thermal Design of Nuclear Reactors

1st Edition

Authors: R. H. S. Winterton
eBook ISBN: 9781483145242
Imprint: Pergamon
Published Date: 1st January 1981
Page Count: 202
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Table of Contents

Other Titles of Interest

Preface

Chapter 1: Summary of Reactor Physics

Publisher Summary

INTRODUCTION

FISSION

NEUTRON FLUX AND REACTION CROSS-SECTIONS

CRITICALITY

MODERATORS

BREEDING

THE MULTIPLICATION CONSTANT

NEUTRON FLUX DISTRIBUTION

PRACTICAL REACTOR SYSTEMS

SUMMARY

Chapter 2: Reactor Systems

Publisher Summary

INTRODUCTION

THE PRESSURIZED WATER REACTOR

THE BOILING WATER REACTOR

THE GAS-COOLED REACTOR—THE AGR

THE SODIUM-COOLED FAST BREEDER REACTOR

Chapter 3: Fuel-Rod Design

Publisher Summary

INTRODUCTION

TEMPERATURE DISTRIBUTION IN A CYLINDRICAL FUEL PELLET

Allowance for variations in conductivity and heat generation

Effect of porosity on UO2 thermal conductivity

Measurements of UO2 thermal conductivity

HEAT TRANSFER IN THE GAP BETWEEN FUEL AND CLADDING

HEAT TRANSFER THROUGH CYLINDRICAL CLADDING

FISSION GAS RELEASE

DETAILS OF FUEL ROD CONSTRUCTION

Problems

Chapter 4: Forced-Convection Heat Transfer

Publisher Summary

INTRODUCTION

HEAT-TRANSFER COEFFICIENT AND DIMENSIONAL ANALYSIS

HEAT-TRANSFER CORRELATIONS FOR NON-METALS

LIQUID-METAL HEAT TRANSFER

COMPARISON OF COOLANTS

IMPROVEMENT OF HEAT TRANSFER USING FINS

IMPROVEMENT OF HEAT TRANSFER BY ROUGHENING THE SURFACE

Problems

Chapter 5: Boiling Heat Transfer

Publisher Summary

INTRODUCTION

NUCLEATION

TYPES OF BOILING

FLOW REGIMES IN FORCED-CONVECTION BOILING

Quality, void fraction and slip ratio

HEAT-TRANSFER CORRELATIONS FOR FLOW BOILING

Film boiling

CRITICAL HEAT-FLUX CORRELATIONS FOR FORCED-CONVECTION BOILING OF WATER

Correlations for bulk boiling

Problems

Chapter 6: Fluid Flow

Publisher Summary

INTRODUCTION

PRESSURE DROP WITH A LIQUID COOLANT

PUMPING POWER

PRESSURE DROP WITH A GASEOUS COOLANT

PRESSURE DROP WITH A TWO-PHASE MIXTURE

CRITICAL FLOW THROUGH BURST PIPES

Problems

Chapter 7: Safety Analysis

Publisher Summary

INTRODUCTION

TIMESCALES OF THE TRANSIENT FLOW AND HEAT-TRANSFER PROCESSES

THE SOURCES OF HEAT

SIMPLE MODEL FOR CLAD TEMPERATURE DURING TRANSIENT

DISCUSSION OF LOSS OF COOLANT ACCIDENTS

THE PROBABILITY APPROACH TO REACTOR SAFETY

THE SODIUM-COOLED FAST REACTOR

Problems

Chapter 8: Core Thermohydraulic Design

Publisher Summary

INTRODUCTION

MAXIMUM CAN TEMPERATURE IN A COOLANT CHANNEL

The maximum fuel temperature

MINIMUM CRITICAL HEAT-FLUX RATIO

HOT-CHANNEL FACTORS

GAGS

SUBCHANNEL ANALYSIS

INCREASING HEAT OUTPUT IN GAS-COOLED REACTORS

MAXIMISING STEAM PRODUCTION SUBJECT TO FIXED CRITICAL HEAT FLUX RATIO

Problems

Chapter 9: Steam Cycles

Publisher Summary

INTRODUCTION

THE TEMPERATURE-ENTHALPY DIAGRAM

THE BASIC RANKINE CYCLE

FEED WATER HEATING (REGENERATION)

PRACTICAL CYCLES FOR WATER REACTORS

PUMPING POWER AND OTHER LOSSES

RADIOACTIVE STEAM IN THE BWR

CYCLES FOR HIGH-TEMPERATURE REACTORS

NET PLANT EFFICIENCY

COMBINED HEAT AND POWER GENERATION

Problems

Chapter 10: Fusion Reactors

Publisher Summary

INTRODUCTION

MAGNETIC CONFINEMENT

THERMAL DESIGN

INERTIAL CONFINEMENT

FLUID FLOW EFFECTS IN STRONG MAGNETIC FIELDS

HEAT-TRANSFER EFFECTS IN STRONG MAGNETIC FIELDS

COMPARISON OF COOLANTS

TRANSIENT HEATING PROBLEMS

Notation

APPENDIX 1: Temperature Distribution Following Sudden Total Loss of Cooling

APPENDIX 2: Properties of Coolants

APPENDIX 3: Conversion Factors

APPENDIX 4: Answers to Selected Problems

APPENDIX 5

INDEX

Details

No. of pages:
202
Language:
English
Copyright:
© Pergamon 1981
Published:
Imprint:
Pergamon
eBook ISBN:
9781483145242

About the Author

R. H. S. Winterton