Robert E Masterson
Introduction to Nuclear Reactor Physics
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Robert E Masterson
Introduction to Nuclear Reactor Physics
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INTRODUCTION TO NUCLEAR REACTOR PHYSICS is the most comprehensive, modern and readable textbook for this course/module.
INTRODUCTION TO NUCLEAR REACTOR PHYSICS is the most comprehensive, modern and readable textbook for this course/module.
Produktdetails
- Produktdetails
- Verlag: CRC Press
- Seitenzahl: 1079
- Erscheinungstermin: 27. November 2017
- Englisch
- Abmessung: 261mm x 209mm x 48mm
- Gewicht: 2207g
- ISBN-13: 9781498751483
- ISBN-10: 1498751482
- Artikelnr.: 48748992
- Verlag: CRC Press
- Seitenzahl: 1079
- Erscheinungstermin: 27. November 2017
- Englisch
- Abmessung: 261mm x 209mm x 48mm
- Gewicht: 2207g
- ISBN-13: 9781498751483
- ISBN-10: 1498751482
- Artikelnr.: 48748992
Robert E. Masterson (1950-2020) held MS and PhD degrees in nuclear engineering from the Massachusetts Institute of Technology, and he worked for Westinghouse Nuclear Energy Systems. He was an Affiliate Professor of Nuclear Science and Engineering at Virginia Tech University in Blacksburg, Virginia. Dr. Masterson published extensively in the journals of the ANS and had over 20 years of experience in the field of nuclear science and engineering. He had an extensive background in the fields of reactor safety, reactor design and analysis, reactor thermal hydraulics, numerical analysis, reactor physics, reactor dynamics, nuclear medicine, and nuclear particle transport. He was a member of the American Nuclear Society. His first textbook with CRC Press, Nuclear Engineering Fundamentals: A Practical Perspective, was published in 2017.
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
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
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
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