Neutronic Analysis For Nuclear Reactor Systems
This book covers the entire spectrum of the science and technology of nuclear reactor systems, from underlying physics, to next generation system applications and beyond. Beginning with neutron physics background and modeling of transport and diffusion, this self-contained learning tool progresses step-by-step to discussions of reactor kinetics, dynamics, and stability that will be invaluable to anyone with a college-level mathematics background wishing to develop an understanding of nuclear po…
Read More ↓Title Statements
- Full title :Neutronic Analysis For Nuclear Reactor Systems / by Bahman Zohuri.
Summary
This book covers the entire spectrum of the science and technology of nuclear reactor systems, from underlying physics, to next generation system applications and beyond. Beginning with neutron physics background and modeling of transport and diffusion, this self-contained learning tool progresses step-by-step to discussions of reactor kinetics, dynamics, and stability that will be invaluable to anyone with a college-level mathematics background wishing to develop an understanding of nuclear power. From fuels and reactions to full systems and plants, the author provides a clear picture of how nuclear energy works, how it can be optimized for safety and efficiency, and why it is important to the future.
Read More ↓Edition Statements
- Publication Date:2017
Publication Statements
- Publisher(s):Springer International Publishing
- Place of Publication:Cham
- Language:eng
- Publication Date:2017
The Physical Object
- Description:1 recurs en línia (1 recurs en línia (XXII, 551 pàgines 148 il·lustracions, 58 il·lustracions en color))
Edition Identifiers
- ISBN:9783319429649, 3319429647
- oclc:on1120576926
Table of Contents
Conté: Neutron Physics Background -- Modeling Neutron Transport and Interactions -- Spatial Effects in Modeling Neutron Diffusion -- One Group Models -- Energy Effects in Modeling Neutron Diffusion -- Two Group Models -- Numerical Methods in Modeling Neutron Diffusion -- Slowing Down Theory -- Resonance Processing -- Heterogeneous Reactors and Wigner Seitz Cells -- Thermal Spectra and Thermal Cross Sections -- Perturbation Theory for Reactor Neutronics -- Reactor Kinetics and Point Kinetics -- Reactor Dynamics -- Reactor Stability -- Numerical Modeling for Time Dependent Problems -- Fission Product Buildup and Decay -- Fuel Burnup and Fuel Management -- Appendix A: Laplace Transforms -- Appendix B: Transfer Functions and Bode Plots -- Index
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