Nuclear reactor / R. K. Singal.

Format:

Book

Author/Creator:

Singal, R. K., author.

Language:

English

Subjects (All):

Nuclear reactors.

Nuclear physics.

Physical Description:

1 online resource (209 pages)

Edition:

1st ed.

Place of Publication:

Daryaganj, New Delhi, India : New Age International (P) Ltd., Publishers, 2015.

Language Note:

English

Contents:

Cover

Preface

Contents

Part-I Theory

Chapter 1. Nuclear Energy Resources

1.1 Introduction

1.2 The Neutron

1.2.1 Neutron Energy

1.2.2 Thermal Neutrons

1.3 Nuclear Processes

1.3.1 Fusion Process

1.3.2 Fission Process

1.3.3 Radioactivity

1.4 Nuclear Fuels

1.4.1 Fuel Cycle

1.4.2 Fuel Cycle with Reprocessing

1.4.3 Fuel Breeding

1.4.4 Deuterium

1.5 Share of Nuclear Energy

1.6 Indian Nuclear Programme

Question Bank

Chapter 2. Nuclear Reactor Engineering

2.1 Introduction

2.2 Chain Reaction

2.3 Nuclear Cross-sections

2.3.1 Neutron Beam

2.3.2 Microscopic Cross-section

2.3.3 Neutron Flux

2.3.4 Reaction Rate

2.3.5 Neutron Scattering

2.3.6 Neutron Moderation

2.3.7 Neutron Absorption

2.3.8 Neutron Reflection

2.4 Variation of Neutron Cross-section with Neutron Energy

2.5 Neutron Life Cycle

2.5.1 Theory of Nuclear Reactor

2.6 Reactor Configuration

2.6.1 Fuel Rods

2.6.2 Moderators

2.6.3 Coolants

2.6.4 Control Rods

2.6.5 Chemical-shim

2.6.6 Structural Materials

2.7 Classification of Nuclear Reactors

Part-II Design

Chapter 3. Pressurized Water Reactors

3.1 Introduction

3.2 Reactor Assembly

3.2.1 Pressure Vessel

3.2.2 Coolant and Moderator

3.2.3 Reactor Core

3.2.4 Control Rods and Drives

3.3 Primary Loop

3.3.1 Steam Generator

3.3.2 Pressurizer

3.3.3 Primary Pumps

3.3.4 Piping and Valves

3.4 Pressure Changes in Pressurizer

3.5 Chemical-Shim Control

3.6 Pressurized Heavy Water Reactor (PHWR)

3.7 CANDU Reactor

Chapter 4. Boiling Water Reactors

4.1 Introduction

4.2 Recirculation Ratio

4.3 Load Control by Recirculation Change

4.3.1 Recirculation System

4.3.2 Recirculation Pumps

4.4 Reactor Assembly

4.4.1 Core

4.4.2 Control Rods.

4.4.3 Control Rod Drive System

4.4.4 Steam Generation

4.5 Reactor Pressure Vessel

Chapter 5. Gas-cooled Reactors

5.1 Introduction

5.2 Magnox Gas-cooled Reactor

5.3 Advanced Gas-cooled Reactor (AGR)

5.4 High-temperature Gas-cooled Reactor (HTGR)

5.4.1 Reactor Vessel

5.4.2 Control System

5.4.3 Primary Heat Transfer System

5.4.4 Steam Plant

5.4.5 Decay Heat Removal

5.5 Thorium High Temperature Reactor

5.6 Primary Cooling System

5.6.1 Steam Generator

5.6.2 Gas Circulators

Chapter 6. Fast Breeder Reactors

6.1 Introduction

6.2 Breeding Reactors

6.2.1 Breeding Ratios

6.2.2 Fuel Production Constants

6.2.3 Doubling Time

6.3 Types of Breeder Reactors

6.3.1 Loop-type LMFBR

6.3.2 Pool-type LMFBR

6.4 Loop Type Breeder Reactor

6.4.1 Reactor Core

6.4.2 The Reactor Vessel

6.4.3 Heat Transfer System

6.4.4 Intermediate Heat Exchangers

6.4.5 Steam Generator

6.4.6 Evaporators and Superheaters

6.4.7 Sodium Pump

6.5 Residual Heat Removal System

6.5.1 Steam By-pass

6.5.2 Steam-generator Heat Removal

6.5.3 Reactor Heat Removal

6.6 Design Data of Loop Type Breeder Reactor

6.7 Pool Type Breeder Reactor

6.7.1 Design Data of Super Phenix Mark I Reactor Plant

6.7.2 Reactor Vessel

6.7.3 Reactor Core

6.7.4 Fuel Assemblies

6.7.5 Fertile Assemblies

6.7.6 Control and Shutdown Rods

6.7.7 Heat Transfer Systems

6.7.8 Steam Generator

6.7.9 Decay-heat Removal

6.8 Gas Cooled Fast Breeder Reactor (GCFBR)

6.8.1 Reactor Core

6.8.2 Fuel Rods

6.8.3 Steam Generator

Chapter 7. Fuel Handling Systems

7.1 Introduction

7.2 Refuelling System

7.2.1 Pressurized Water Reactors

7.2.2 Boiling Water Reactor

7.2.3 Gas-cooled Reactor

7.3 Spent Fuel Storage

7.3.1 Radioactivity.

7.3.2 Properties of Emissions or Decays

7.3.3 Decay Rates and Half Lives

7.3.4 Half Lives of Important Isotopes

7.3.5 Fuel Storage Cooling System

7.3.6 Pool Water Requirement

7.4 Fuel Reprocessing

7.4.1 Chemical Process

7.4.2 Solidification of High Level Wastes

7.4.3 Disposal

7.5 Spent Fuel Storage

7.5.1 High-level Wastes

7.5.2 Biological Effects of High Level Wastes

7.5.3 Burial Sites

Chapter 8. Primary Coolant Purification System

8.1 Introduction

8.2 Activation of Primary Coolant in Water Reactors

8.2.1 Activation of Corrosion and Wear Products

8.2.2 Neutron Capture in Water

8.2.3 Other Impurities

8.2.4 Tritium Gas Production

8.3 Heavy Water Reactor

8.3.1 Tritium Gas Production

8.3.2 Neutron Capture in Heavy Water

8.4 High Temperature Gas-cooled Reactor

8.5 Fast Breeder Reactors

8.6 Coolant Quality Requirements

8.6.1 PWR Primary Loop

8.6.2 BWR Coolant Loop

8.7 Purification Systems Requirements

8.7.1 PWR Purification System

8.7.2 BWR Purification System

8.7.3 Helium Purification System

8.8 Demineralizers

8.8.1 Deep Bed Demineralizer

8.8.2 Ground Resin Demineralizer

8.9 Boron Management

8.9.1 Boric Acid Recovery

8.10 Helium Purification and Hydrogen Removal System

Chapter 9. Reactor Protection and Control Systems

9.1 Introduction

9.2 Reactor Protection System

9.2.1 Design of Protection System

9.2.2 Parameters to be Monitored by Protection System

9.3 Protection Systems for Different Reactors

9.3.1 Pressurized Water Reactor

9.3.2 Boiling Water Reactor

9.3.3 Gas Cooled Reactor

9.4 Control System

9.5 Process Control System

9.6 Radiation Monitoring System

Part-III Fabrication

Chapter 10. Construction Materials for Reactors

10.1 Introduction.

10.2 Construction of Nuclear Reactor

10.3 Operational Parameters of Reactors

10.3.1 Nuclear Parameters

10.3.2 Thermo-mechanical Parameters

10.3.3 Corrosion and Erosion

10.4 Types of Corrosion

10.5 Heat Transfer

10.6 Economical Parameters

Chapter 11. Nuclear Properties of Stainless Steel

11.1 Use of Austenitic Stainless Steels

11.2 Nuclear Properties of Stainless Steel

11.3 Corrosion Resistance of Stainless Steel

11.3.1 Corrosion of Austenitic Stainless Steels by High-purity Water

11.3.2 Corrosion of Austenitic Stainless Steels by Molten Metals

11.3.3 Corrosion of Stainless Steels by Hot Gases

11.3.4 Corrosion of Stainless Steels by Nuclear Fuels and Fission Products

11.3.5 Corrosion of Stainless Steel by Sea Water

11.4 Thermo-mechanical Properties of Stainless Steel

11.5 Technological Properties of Stainless Steel

11.6 Compatibility of Stainless Steel with Gasketing and Insulating Materials

11.7 Economics of Use of Stainless Steel

Chapter 12. Reactor Components

12.1 Nuclear Components

12.1.1 Reactor Pressure Vessel

12.1.2 Steam Generator

12.1.3 Pressure Vessels and Tanks

12.1.4 Heat Exchangers

12.1.5 Pumps

12.1.6 Valves

12.1.7 Piping

12.2 Conclusion

Chapter 13. Pressure Containing Welds

13.1 Introduction

13.2 Pressure Containing Welds

13.3 Design and Service Requirements

13.4 Seismic Loading

13.4.1 Thermo-mechanical Parameters

13.4.2 Corrosion and Erosion

13.4.3 Nuclear Parameters

13.4.4 Additional Requirements

13.5 Design Controls

13.5.1 Operating Cycle

13.5.2 Design bases for Protection against Natural Phenomenon

13.5.3 Fire Protection

13.5.4 Environmental and Missile Design Bases

13.5.5 Stress Analysis and Control

13.6 Metallurgical Controls

13.6.1 Fracture Prevention

13.6.2 Impact Properties.

13.6.3 Material Control

13.7 Fabrication Controls

13.7.1 Weld Joint Design

13.7.2 Selection of Filler Metal

13.7.3 Welding Methods

13.8 Quality Assurance

13.9 Inservice Inspection

13.10 Conclusion

Chapter 14. Fabrication and Testing of Heat Exchangers

14.1 Introduction

14.2 Technical Requirements of Tube Joint

14.2.1 Types of Tube to Tube-sheet Joints

14.2.2 Tube Expanding Parameters

14.2.3 Tube-end Expansion

14.2.4 Groove Designs

14.2.5 Length of Expansion

14.2.6 Strength and Stability of Joint

14.2.7 Metallurgical Requirements of Welded Tube Joint

14.3 Material Checking

14.3.1 Tubesheets

14.3.2 Tubes

14.3.3 U-tubes

14.4 Calibration of Expanding Tool and Mock-Up Test

14.5 Insertion of Tubes

14.6 Tubesheet Holes and Clearances

14.7 Check List of Material Test Certificates

14.8 Heat Exchanger Tubes

14.9 Ring Out Test for Determination of Internal Stresses

14.10 Stress Relieving of Heat Exchanger Tubes

14.11 Welding of Tubes to Tubesheets

14.11.1 Carbon Steels

14.11.2 Low Alloy Carbon Steels

14.11.3 Chromium - Molybdenum Steels with 1% Cr and 0.5% Mo

14.11.4 Austenitic Stainless Steels (Type 316, 321 and 347)

14.12 Sealing of Joints

14.12.1 Seal Welding

14.12.2 Back Brazing

14.12.3 Rubber Latex

14.12.4 Long Tube Joints

14.13 Testing

14.14 Welding Parameters

14.15 Procedure Qualification for Tube to Tubesheet Welding

14.16 Test Assembly

14.17 Examination

Appendices

Index.

Notes:

Includes index.

Description based on online resource; title from PDF title page (ebrary, viewed December 16, 2014).

ISBN:

81-224-3909-8