Buch, Englisch, 1107 Seiten, Format (B × H): 209 mm x 261 mm, Gewicht: 2207 g
Buch, Englisch, 1107 Seiten, Format (B × H): 209 mm x 261 mm, Gewicht: 2207 g
ISBN: 978-1-4987-5148-3
Verlag: CRC Press
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.
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1. Nuclear Power in the World Today 2. Neutrons and Other Important Particles of Reactor Physics 3. Nuclear Particles, Processes, and Reactions 4. Nuclear Cross Sections, Reaction Probabilities, and Reaction Rates 5. Cross Section Libraries and Sources of Practical Nuclear Data 6. Nuclear Fuels, Nuclear Structure, the Mass Defect, and Radioactive Decay 7. Nuclear Fission and Nuclear Energy Production 8. Neutron Slowing Down Theory, Neutron Moderators, and Reactor Coolants 9. The Neutron Multiplication Factor, the Reactivity, and the Four-Factor Formula 10. Neutron Leakage, Reactor Criticality, and the Six-Factor Formula 11. An Introduction to Neutron Diffusion Theory and Fick’s Law of Diffusion 12. Multigroup Neutron Diffusion Theory 13. Solutions to the Steady-State Neutron Diffusion Equation 14. Solving the Neutron Diffusion Equation with a Radioactive Source Term 15. Time-Dependent Reactors and Their Behavior 16. The Point Kinetics Approximation and the Inhour Equation 17. Burnup, Depletion, and Temperature Feedback 18. Long-Term Changes to the Reactivity of the Core 19. Fuel Assembly Homogenization and Reaction Rate Conservation 20. Control Rods, Burnable Poisons, and Chemical Shim 21. Fission Products, Xenon Transients, and Reactor Accidents 22. An Introduction to Neutron Transport Theory 23. The Monte Carlo Method and Its Applications to Nuclear Science and Engineering