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Titlebook: Neutronic Analysis For Nuclear Reactor Systems; Bahman Zohuri Book 20171st edition Springer International Publishing Switzerland 2017 Hete

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書目名稱Neutronic Analysis For Nuclear Reactor Systems
編輯Bahman Zohuri
視頻videohttp://file.papertrans.cn/665/664696/664696.mp4
概述Covers the fundamentals of neutronic analysis for nuclear reactor systems in order to help readers understand nuclear reactor theory.Applies the described principles to nuclear reactor power systems.A
圖書封面Titlebook: Neutronic Analysis For Nuclear Reactor Systems;  Bahman Zohuri Book 20171st edition Springer International Publishing Switzerland 2017 Hete
描述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.
出版日期Book 20171st edition
關(guān)鍵詞Heterogeneous Reactors; Modeling Nuclear Plants; Neutron Diffusion; Nuclear Energy; Nuclear Engineering;
版次1
doihttps://doi.org/10.1007/978-3-319-42964-9
isbn_softcover978-3-319-82706-3
isbn_ebook978-3-319-42964-9
copyrightSpringer International Publishing Switzerland 2017
The information of publication is updating

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Reactor Kinetics and Point Kinetics,f changing reactivity. A basic approach using a minimum of mathematics has been followed. Emphasis has been placed on distinguishing between prompt and delayed neutrons and showing relationships among reactor variables, .., period, neutron density, and power level.
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Resonance Processing,nt virtues of the optical model is that it takes into account the existence of . or . in the total cross section as part of neutronic analysis for nuclear reactor systems. For resonances of energy levels, which are spaced widely apart, we can describe the energy dependency of the absorption cross section via the .–.-..
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