Introduction to Nuclear Reactor Physics, Robert E. Masterson, 1498751482, 9781498751483

INTRODUCTION TO NUCLEAR REACTOR PHYSICS is the most comprehensive, modern and readable textbook for this course/module. It explains reactors, fuel cycles, radioisotopes, radioactive materials, design, and operation. Chain reaction and fission reactor concepts are presented, plus advanced coverage including neutron diffusion theory. The diffusion equation, Fisk’s Law, and steady state/time-dependent reactor behavior. Numerical and analytical solutions are also covered. The text has full color illustrations throughout, and a wide range of student learning features.

Covers all major topics needed for courses in Nuclear Reactor Physics, both undergraduate and graduate level
Provides the most up-to-date information on reactor designs and numerical/computer methods
Written in a student-oriented style, with full-color diagrams and photographs throughout
Offers numerous examples, questions, problems, and boxed features
Includes a complete solutions manual and electronic versions of figures for instructors

Preface

Chapter 1 : Nuclear Power in the World Today
Chapter 2 : Neutrons and Other Important Particles of Reactor Physics
Chapter 3 : Nuclear Particles, Processes, and Reactions
Chapter 4 : Nuclear Cross Sections, Reaction Probabilities, and Reaction Rates
Chapter 5 : Cross Section Libraries and Sources of Practical Nuclear Data
Chapter 6 : Nuclear Fuels, Nuclear Structure, the Mass Defect, and Radioactive Decay
Chapter 7 : Nuclear Fission and Nuclear Energy Production
Chapter 8 : Neutron Slowing Down Theory, Neutron Moderators, and Reactor Coolants
Chapter 9 : The Neutron Multiplication Factor, the Reactivity, and the Four-Factor Formula
Chapter 10 : Neutron Leakage, Reactor Criticality, and the Six-Factor Formula
Chapter 11 : An Introduction to Neutron Diffusion Theory and Fick’s Law of Diffusion
Chapter 12 : Multigroup Neutron Diffusion Theory
Chapter 13 : Solutions to the Steady-State Neutron Diffusion Equation
Chapter 14 : Solving the Neutron Diffusion Equation with a Radioactive Source Term
Chapter 15 : Time-Dependent Reactors and Their Behavior
Chapter 16 : The Point Kinetics Approximation and the Inhour Equation
Chapter 17 : Burnup, Depletion, and Temperature Feedback
Chapter 18 : Long-Term Changes to the Reactivity of the Core
Chapter 19 : Fuel Assembly Homogenization and Reaction Rate Conservation
Chapter 20 : Control Rods, Burnable Poisons, and Chemical Shim
Chapter 21 : Fission Products, Xenon Transients, and Reactor Accidents
Chapter 22 : An Introduction to Neutron Transport Theory
Chapter 23 : The Monte Carlo Method and Its Applications to Nuclear Science and Engineering

Index

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