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Neutronic analysis for nuclear react...
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Zohuri, Bahman.
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Neutronic analysis for nuclear reactor systems
紀錄類型:
書目-電子資源 : Monograph/item
正題名/作者:
Neutronic analysis for nuclear reactor systems/ by Bahman Zohuri.
作者:
Zohuri, Bahman.
出版者:
Cham :Springer International Publishing : : 2017.,
面頁冊數:
xxii, 551 p. :ill., digital ;24 cm.
內容註:
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.
Contained By:
Springer eBooks
標題:
Nuclear reactors. -
電子資源:
http://dx.doi.org/10.1007/978-3-319-42964-9
ISBN:
9783319429649
Neutronic analysis for nuclear reactor systems
Zohuri, Bahman.
Neutronic analysis for nuclear reactor systems
[electronic resource] /by Bahman Zohuri. - Cham :Springer International Publishing :2017. - xxii, 551 p. :ill., digital ;24 cm.
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.
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.
ISBN: 9783319429649
Standard No.: 10.1007/978-3-319-42964-9doiSubjects--Topical Terms:
673875
Nuclear reactors.
LC Class. No.: TK9202
Dewey Class. No.: 621.483
Neutronic analysis for nuclear reactor systems
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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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