Thermal Design of Nuclear Reactors
- 1st Edition - November 9, 2013
- Latest edition
- Author: R. H. S. Winterton
- Language: English
- Paperback ISBN:9 7 8 - 1 - 4 8 3 1 - 1 2 8 2 - 4
- eBook ISBN:9 7 8 - 1 - 4 8 3 1 - 4 5 2 4 - 2
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
- Edition: 1
- Latest edition
- Published: November 9, 2013
- Language: English
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