Nuclear Reactor Physics and Engineering (eBook)
1198 Seiten
Wiley (Verlag)
978-1-394-28356-9 (ISBN)
Essential guide to analyzing nuclear energy systems, with focus on reactor physics, fuel cycle, system dynamics, thermal-hydraulics, and economics.
Nuclear Reactor Physics and Engineering highlights efforts in utilizing low enrichment uranium fuel as a substitute for carbon-based fuels in energy generation and provides an overview of important aspects of nuclear reactor physics utilizing the neutron diffusion equation for major reactor designs and MATLAB software for system analysis, with exercises illustrating key points and design parameters as supplementary material.
This revised and updated Second Edition reflects key findings of the 2023 National Academy of Sciences (NAS) report and discusses physical and engineering characteristics of advanced nuclear reactors, especially in the form of small modular reactors that have the potential to provide enhanced safety and economics, as well as effective long-term management of used nuclear fuel in geological repositories.
Key topics explored in the updated edition of Nuclear Reactor Physics and Engineering include:
- Impact of the use of high-assay low enrichment uranium (HALEU) fuel as a new efficient nuclear fuel
- Advantages resulting from combined uses of light water reactor and sodium-cooled fast reactor with fuel reprocessing
- Fundamental nuclear reactor physics, nuclear reactor system analysis, and lattice physics analysis for reactor cores
- Nuclear fuel cycle analysis, nuclear plant simulation and control, and management of used nuclear fuel
- Economic analysis of nuclear electricity and thermal-hydraulic analysis of nuclear systems.
With a wealth of all-new information detailing the state of the art in the field, Nuclear Reactor Physics and Engineering is an invaluable reference on the subject for undergraduate and graduate students in nuclear engineering, as well as practicing engineers involved with nuclear power plants.
John C. Lee, PhD, has been on the nuclear engineering faculty at the University of Michigan since 1974 and served as the department chair for six years. He has published two Wiley books, Risk and Safety Analysis of Nuclear Systems (with N.J. McCormick, 2011, 2017 second printing) and Nuclear Reactor Physics and Engineering (2020). He has served on two U.S. National Academy of Sciences committees, including the recent committee on advanced nuclear reactors and used nuclear fuel. Dr. Lee is a Fellow of the American Nuclear Society.
List of Figures
Figure 1.1 Nuclear power plant evolution.
Figure 1.2 Overall layout of a PWR plant.
Figure 1.3 Schematic diagram of a PWR plant.
Figure 1.6 Cross-section view of PWR fuel assemblies for the AP1000 design.
Figure 1.8 Cutaway view of Mark I BWR containment structure.
Figure 1.10 BWR fuel bundle cluster illustrating the W-W and N-N gaps.
Figure 1.12 Sodium-cooled fast reactor plant.
Figure 1.13 Top view of the reactor core of a SFR plant.
Figure 1.14 Very high-temperature reactor plant.
Figure 1.15 Top view inside the reactor vessel of a VHTR plant.
Figure 1.16 TRISO particle, pin cell, and prismatic fuel assembly for the VHTR plant.
Figure 1.17 Molten-salt reactor plant.
Figure 1.18 Top view inside a MSR reactor vessel.
Figure 1.19 Schematic illustration of the NuScale module.
Figure 1.20 Micro modular reactor.
Figure 2.1 A collimated beam of neutron incident on a slab.
Figure 2.2 Energy levels for a compound nucleus.
Figure 2.6 Energy spectrum of fission neutrons emitted for U, ENDF/B-VIII.0 MF = 5, MT = 18 and 455.
Figure 2.7 Velocities before and after the collision in Lab and CM systems.
Figure 2.9 Resonance cross section as a function of neutron energy.
Figure 2.10 Scattering of collimated beam into solid angle around in distance .
Figure 2.11 Solid angle with azimuthal symmetry.
Figure 2.12 Elastic scattering kernel as a function of outgoing neutron energy.
Figure 2.13 Total cross section of B, ENDF/B-VIII.
Figure 2.14 Total cross section of C, ENDF/B-VIII.
Figure 2.15 Radiative capture cross section for U, ENDF/B-VIII.
Figure 2.16 Radiative capture cross section for Pu, ENDF/B-VIII.
Figure 3.1 Differential volume elements in physical and velocity spaces.
Figure 3.2 Differential cylinder for visualizing angular flux as neutron current.
Figure 3.3 Neutron flux for a collimated neutron beam.
Figure 3.4 Projection of a unit cross-sectional area.
Figure 3.5 Relationship between vector current and net current .
Figure 3.6 Maxwell–Boltzmann distribution as a function of speed.
Figure 4.1 Unit cross-sectional area for the negative partial current.
Figure 4.2 Directional vector projected via polar and azimuthal angles.
Figure 4.3 Physical interpretation of transport mean free path .
Figure 5.1 Linear extrapolation of flux at a free surface.
Figure 5.2 Two material regions separated by vacuum.
Figure 5.3 Planar source in slab geometry.
Figure 5.4 Closed contour in the Fourier domain -space.
Figure 5.5 Extrapolated boundary for slab geometry.
Figure 5.6 Two-region slab with plane source.
Figure 5.7 Construction of a plane source from annular ring sources.
Figure 5.8 Three lowest-order flux modes for slab reactor of height .
Figure 5.9 Life cycle of neutrons illustrating the six-factor formula.
Figure 6.1 Discretization scheme for the flux and flux derivative.
Figure 6.2 Discretized flux distribution at the vacuum boundary.
Figure 6.3 Flux distribution near a reflecting boundary at .
Figure 6.4 Inner and outer iterations for solution of the diffusion equation.
Figure 6.5 Finite-difference mesh structure for .
Figure 6.6 2-D discretization scheme.
Figure 6.7 Two-dimensional finite-difference structure.
Figure 6.8 2-D line relaxation scheme.
Figure 6.9 Successive relaxation scheme.
Figure 6.10 NEM geometry for solution in the -direction.
Figure 6.11 Illustration of the homogenous and heterogeneous fluxes.
Figure 7.1 Lethargy variable and energy group structure.
Figure 8.1 Schematics of decay chains for fission product Br.
Figure 8.2 Transient and stable solutions of the point kinetic equations with dollar.
Figure 8.3 Reactivity versus roots of the inhour equation
Figure 8.4 Transfer function representing the output-to-input ratio.
Figure 8.5 Open-loop transfer function connecting control input to output together with controller .
Figure 8.6 Simulink setup for the pulse source solution of Example 8.2.
Figure 8.7 Simulink pulse source output of Example 8.2.
Figure 8.8 Phase plane solution of the Ergen–Weinberg model.
Figure 8.9 Time-domain behavior of the Ergen–Weinberg model.
Figure 8.10 Time-domain behavior of the Nordheim–Fuchs power excursion model.
Figure 8.11 Inverse multiplication as a function of fuel mass.
Figure 8.14 Nyquist diagram for , Example 8.4.
Figure 8.15 Bode diagram for , Example 8.4, indicating db and .
Figure 8.16 Bode diagram for open-loop reactor transfer function .
Figure 9.1 Phase volume representing the neutron balance.
Figure 9.2 Lethargy variable and average lethargy increase per collision.
| Erscheint lt. Verlag | 3.12.2024 |
|---|---|
| Sprache | englisch |
| Themenwelt | Technik ► Elektrotechnik / Energietechnik |
| Schlagworte | MATLAB Simulink toolbox • nuclear electricity • Nuclear fuel cycle • nuclear plant control • nuclear plant simulation • Nuclear Reactor Physics • nuclear system analysis • used nuclear fuel management |
| ISBN-10 | 1-394-28356-3 / 1394283563 |
| ISBN-13 | 978-1-394-28356-9 / 9781394283569 |
| Informationen gemäß Produktsicherheitsverordnung (GPSR) | |
| Haben Sie eine Frage zum Produkt? |
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