INTRODUCTION TO NUCLEAR REACTOR PHYSICS
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- Author: ROBERT E. MASTERSON
- ISBN: 9781498751483
- Availability: In Stock
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ABOUT THE BOOK
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.
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