9780201824988

The third edition of this popular book is updated to include a completely revised discussion of reactor technology, an improved discussion of the reactor physics, and a more detailed discussion of basic nuclear physics and models. bull; Introduces the basics of the shell model of the nucleus and a beginning discussion of quantum mechanics. Discusses both U.S. and non-U.S. reactor designs, as well as advanced reactors. Provides for a more detailed understanding of both reactor statics and kinetics. Includes updated information on reactor acidents and safety.

Anthony Baratta is currently a Professor of Nuclear Engineering at The Pennsylvania State University and Director of the Nuclear Safety Center. He received the B.A/B.S. degrees in physics/applied physics from Columbia University in 1968 and the M.S. and Ph.D. degrees in physics from Brown University in 1970 and 1978, respectively. His research interests and contributions include reactor safety, reactor kinetics and physics, and the effects of radiation on materials. He has authored many scientific publications and made numerous presentations. He is an active member of the American Nuclear Society and has appeared on many network television and radio broadcasts as an authority on reactor accidents, including the accident at Three Mile Island.

Nuclear Engineering

1

(5)

Atomic and Nuclear Physics

5

(47)

Fundamental Particles

5

(2)

Atomic and Nuclear Structure

7

(1)

Atomic and Molecular Weight

8

(3)

Atomic and Nuclear Radii

11

(1)

Mass and Energy

11

(3)

Particle Wavelengths

14

(1)

Excited States and Radiation

15

(3)

Nuclear Stability and Radioactive Decay

18

(4)

Radioactivity Calculations

22

(4)

Nuclear Reactions

26

(3)

Binding Energy

29

(4)

Nuclear Models

33

(4)

Gases, Liquids, and Solids

37

(3)

Atom Density

40

(12)

References

44

(1)

Problems

45

(7)

Interaction of Radiation with Matter

52

(65)

Neutron Interactions

52

(2)

Cross-Sections

54

(3)

Neutron Attenuation

57

(3)

Neutron Flux

60

(2)

Neutron Cross-Section Data

62

(6)

Energy Loss in Scattering Collisions

68

(6)

Fission

74

(16)

γ-Ray Interactions with Matter

90

(10)

Charged Particles

100

(17)

References

109

(1)

Problems

110

(7)

Nuclear Reactors and Nuclear Power

117

(113)

The Fission Chain Reaction

117

(2)

Nuclear Reactor Fuels

119

(10)

Non-Nuclear Components of Nuclear Power Plants

129

(4)

Components of Nuclear Reactors

133

(3)

Power Reactors and Nuclear Steam Supply Systems

136

(49)

Nuclear Cycles

185

(16)

Isotope Separation

201

(16)

Fuel Reprocessing

217

(2)

Radioactive Waste Disposal

219

(11)

References

223

(1)

Problems

224

(6)

Neutron Diffusion and Moderation

230

(36)

Neutron Flux

230

(1)

Fick's Law

231

(4)

The Equation of Continuity

235

(2)

The Diffusion Equation

237

(1)

Boundary Conditions

238

(2)

Solutions of the Diffusion Equation

240

(6)

The Diffusion Length

246

(2)

The Group-Diffusion Method

248

(4)

Thermal Neutron Diffusion

252

(5)

Two-Group Calculation of Neutron Moderation

257

(9)

References

260

(1)

Problems

260

(6)

Nuclear Reactor Theory

266

(61)

One-Group Reactor Equation

266

(5)

The Slab Reactor

271

(3)

Other Reactor Shapes

274

(8)

The One-Group Critical Equation

282

(4)

Thermal Reactors

286

(11)

Reflected Reactors

297

(11)

Multigroup Calculations

308

(1)

Heterogeneous Reactors

309

(18)

References

320

(1)

Problems

321

(6)

The Time-Dependent Reactor

327

(76)

Classification of Time Problems

328

(2)

Reactor Kinetics

330

(18)

Control Rods and Chemical Shim

348

(17)

Temperature Effects on Reactivity

365

(11)

Fission Product Poisoning

376

(13)

Core Properties during Lifetime

389

(14)

References

397

(1)

Problems

398

(5)

Heat Removal From Nuclear Reactors

403

(63)

General Thermodynamic Considerations

404

(4)

Heat Generation in Reactors

408

(9)

Heat Flow by Conduction

417

(11)

Heat Transfer to Coolants

428

(13)

Boiling Heat Transfer

441

(9)

Thermal Design of a Reactor

450

(16)

References

457

(2)

Problems

459

(7)

Radiation Protection

466

(82)

History of Radiation Effects

467

(1)

Radiation Units

468

(8)

Some Elementary Biology

476

(3)

The Biological Effects of Radiation

479

(6)

Quantitative Effects of Radiation on the Human Species

485

(10)

Calculations of Radiation Effects

495

(4)

Natural and Man-Made Radiation Sources

499

(7)

Standards of Radiation Protection

506

(5)

Computations of Exposure and Dose

511

(15)

Standards for Intake of Radionuclides

526

(9)

Exposure from γ-Ray Sources

535

(13)

Glossary

539

(3)

References

542

(2)

Problems

544

(4)

Radiation Shielding

548

(64)

Gamma-Ray Shielding: Buildup Factors

549

(10)

Infinite Planar and Disc Sources

559

(7)

The Line Source

566

(5)

Internal Sources

571

(2)

Multilayered Shields

573

(3)

Nuclear Reactor Shielding: Principles of Reactor Shielding

576

(2)

Removal Cross-Sections

578

(6)

The Reactor Shield Design: Removal-Attenuation Calculations

584

(4)

The Removal-Diffusion Method

588

(2)

Exact Methods

590

(5)

Shielding γ-Rays

595

(4)

Coolant Activation

599

(5)

Ducts in Shields

604

(8)

References

605

(1)

Problems

606

(6)

Reactor Licensing, Safety, and The Environment

612

(149)

Governmental Authority and Responsibility

613

(1)

Reactor Licensing

614

(9)

Principles of Nuclear Power Plant Safety

623

(8)

Dispersion of Effluents from Nuclear Facilities

631

(19)

Radiation Doses from Nuclear Plants

650

(19)

Reactor Siting

669

(12)

Reactor Accidents

681

(20)

Accident Risk Analysis

701

(9)

Environmental Radiation Doses

710

(21)

References

721

(2)

Problems

723

(8)

APPENDIXES

I Units and Conversion Factors

731

(6)

II Fundamental Constants and Data

737

(8)

III Vector Operations in Orthogonal Curvilinear Coordinates

745

(6)

IV Thermodynamic and Physical Properties

751

(6)

V Bessel Functions

757

(4)

Index

761

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The New copy of this book will include any supplemental materials advertised. Please check the title of the book to determine if it should include any access cards, study guides, lab manuals, CDs, etc.

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Preface to Third Edition This revision is derived from personal experiences in teaching introductory and advanced level nuclear engineering courses at the undergraduate level. In keeping with the original intent of John Lamarsh, every attempt is made to retain his style and approach to nuclear engineering education. Since the last edition, however, considerable changes have occurred in the industry. The changes include the development of advanced plant designs, the significant scale-back in plant construction, the extensive use of high speed computers, and the opening of the former Eastern Block countries and of the Soviet Union. From a pedagogical view, the World Wide Web allows access to many resources formerly only available in libraries. Attempts are made to include some of these resources in this edition. In an attempt to update the text to include these technologies and to make the text useful for the study of non-western design reactors, extensive changes are made to Chapter 4,Nuclear Reactors and Nuclear Power.The chapter is revised to include a discussion of Soviet-design reactors and technology. The use, projection, and cost of nuclear power worldwide is updated to the latest available information. In Chapter 11,Reactor Licensing and Safety,the Chernobyl accident is discussed along with the latest reactor safety study, NURG 1150. A section is also included that describes non-power nuclear accidents such, as Tokai-Mura. The basic material in Chapters 2-7 is updated to include newer references and to reflect the author's experience in teaching nuclear engineering. Throughout the text, the references are updated were possible to include more recent publications. In many topic areas, references to books that are dated and often out of print had to be retained, since there are no newer ones available. Since these books are usually available in college libraries, they should be available to most readers. Chapter 9 is retained in much its same form but is updated to include a more complete discussion of the SI system of units and of changes in philosophy that have occurred in radiation protection. Since many of these changes have yet to reach general usage, however, the older discussions are still included. As in the second edition, several errors were corrected and undoubtedly new ones introduced. Gremlins never sleep!

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Introduction to Nuclear Engineering

Introduction to Nuclear Engineering

0201824981

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