An Introduction to Nuclear Materials

Covering both fundamental and advanced aspects in an accessible way, this textbook begins with an overview of nuclear reactor systems, helping readers to familiarize themselves with the varied designs. Then the readers are introduced to different possibilities for materials applications in the various sections of nuclear energy systems. Materials selection and life prediction methodologies for nuclear reactors are also presented in relation to creep, corrosion and other degradation mechanisms. An appendix compiles useful property data relevant for nuclear reactor applications.

Throughout the book, there is a thorough coverage of various materials science principles, such as physical and mechanical metallurgy, defects and diffusion and radiation effects on materials, with serious efforts made to establish structure-property correlations wherever possible. With its emphasis on the latest developments and outstanding problems in the field, this is both a valuable introduction and a ready reference for beginners and experienced practitioners alike.

In diesem Buch geht es um Einsatzmöglichkeiten verschiedener Materialien in der Kernenergietechnik. Nach einem allgemeinen Überblick über Aufbau und Funktion von Kernreaktoren werden die verschiedenen Systeme einzeln besprochen.
Die letzten Kapitel befassen sich mit Spezialthemen wie Reaktoren für die Raumfahrt und Fusionsreaktoren. Die Autoren legen viel Wert darauf, Struktur-Eigenschafts-Beziehungen herauszustellen und naturwissenschaftliche Prinzipien aus vielen Disziplinen zu erfassen. Jedes Kapitel wird durch eine Zusammenfassung, Literaturhinweise und Übungsaufgaben abgeschlossen. Kenndaten, die man für Anwendungen in der Praxis braucht, stellt ein Anhang übersichtlich zusammen.

Preface XV

1 Overview of Nuclear Reactor Systems and Fundamentals 1

1.1 Introduction 1

1.2 Types of Nuclear Energy 2

1.3 Neutron Classification 3

1.4 Neutron Sources 3

1.5 Interactions of Neutrons with Matter 3

1.6 Definition of Neutron Flux and Fluence 6

1.7 Neutron Cross Section 7

1.8 Types of Reactors 11

1.9 Materials Selection Criteria 28

1.10 Summary 37

Appendix 1.A 37

Additional Reading Materials 40

2 Fundamental Nature of Materials 43

2.1 Crystal Structure 43

2.2 Crystal Defects 69

2.3 Diffusion 89

Bibliography 110

3 Fundamentals of Radiation Damage 111

3.1 Displacement Threshold 114

3.2 Radiation Damage Models 118

3.3 Summary 125

Bibliography and Suggestions for Further Reading 126

Additional Reading 126

4 Dislocation Theory 127

4.1 Deformation by Slip in Single Crystals 127

4.2 Other Dislocation Characteristics 140

4.3 Dislocations in Different Crystal Structures 160

4.4 Strengthening (Hardening) Mechanisms 167

4.5 Summary 178

Bibliography 180

Additional Reading 180

5 Properties of Materials 181

5.1 Mechanical Properties 181

5.2 Thermophysical Properties 240

Appendix 5.A 260

Appendix 5.B 260

Bibliography and Suggestions for Further Reading 265

Additional Reading 266

6 Radiation Effects on Materials 267

6.1 Microstructural Changes 267

6.2 Mechanical Properties 287

6.3 Radiation Effects on Physical Properties 306

6.4 Radiation Effects on Corrosion Properties 308

6.5 Summary 314

Bibliography 316

7 Nuclear Fuels 319

7.1 Introduction 319

7.2 Metallic Fuels 321

7.3 Ceramic Fuels 347

7.4 Summary 356

Bibliography 357

Additional Reading 358

Appendix A Stress and Strain Tensors 359

Appendix B 367

Index 375

K. Linga Murty has been on the faculty of the Nuclear Engineering department at North Carolina State University since 1981 and has been teaching courses in Nuclear Materials. Dr. Murty received his Ph.D. degree in Applied Physics (Materials) from Cornell University (USA) in 1970. He has been awarded numerous awards including the American Nuclear Society Mishima Award (1993), and is the author or coauthor of more than 260 technical papers.

Indrajit Charit has been a member of the research staff of the Nuclear Engineering department at North Carolina State University since 2005. He received his Ph.D. degree in Metallurgical Engineering from the University of Missouri-Rolla (USA) in 2004. Dr. Charit has spent about 8 years working on various research programs involving structural materials. He has published and/or presented more than 30 papers.

Covering both fundamental and advanced aspects in an accessible way, this textbook begins with an overview of nuclear reactor systems, helping readers to familiarize themselves with the varied designs. Then the readers are introduced to different possibilities for materials applications in the various sections of nuclear energy systems. Materials selection and life prediction methodologies for nuclear reactors are also presented in relation to creep, corrosion and other degradation mechanisms. An appendix compiles useful property data relevant for nuclear reactor applications.

Throughout the book, there is a thorough coverage of various materials science principles, such as physical and mechanical metallurgy, defects and diffusion and radiation effects on materials, with serious efforts made to establish structure-property correlations wherever possible. With its emphasis on the latest developments and outstanding problems in the field, this is both a valuable introduction and a ready reference for beginners and experienced practitioners alike.