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Neutronic analysis for nuclear react...

Zohuri, Bahman.

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Neutronic analysis for nuclear reactor systems

Record Type:	Electronic resources : Monograph/item
Title/Author:	Neutronic analysis for nuclear reactor systems/ by Bahman Zohuri.
Author:	Zohuri, Bahman.
Published:	Cham :Springer International Publishing : : 2019.,
Description:	xxii, 663 p. :ill., digital ;24 cm.
[NT 15003449]:	Neutron Physics Background -- Modeling Neutron Transport and Interactions -- Spatial Effects in Modeling Neutron Diffusion -- Energy effects in modeling neutron diffusion -- 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 -- Reactor Dynamics -- Reactor Stability -- Numerical Modeling for Time Dependent Problems -- Fission product buildup and decay -- Fuel burn-up and fuel management -- Why nuclear power energy -- Small Modular Reactors and their innovative designs -- Design and analysis of a nuclear reactor core for small modular reactors.
Contained By:	Springer eBooks
Subject:	Nuclear reactors. -
Online resource:	https://doi.org/10.1007/978-3-030-04906-5
ISBN:	9783030049065

Neutronic analysis for nuclear reactor systems
Zohuri, Bahman.

Neutronic analysis for nuclear reactor systems[electronic resource] /by Bahman Zohuri. - 2nd ed. - Cham :Springer International Publishing :2019. - xxii, 663 p. :ill., digital ;24 cm.

Neutron Physics Background -- Modeling Neutron Transport and Interactions -- Spatial Effects in Modeling Neutron Diffusion -- Energy effects in modeling neutron diffusion -- 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 -- Reactor Dynamics -- Reactor Stability -- Numerical Modeling for Time Dependent Problems -- Fission product buildup and decay -- Fuel burn-up and fuel management -- Why nuclear power energy -- Small Modular Reactors and their innovative designs -- Design and analysis of a nuclear reactor core for small modular reactors.

This expanded new edition develops the theory of nuclear reactors from the fundamentals of fission to the operating characteristics of modern reactors. The first half of the book emphasizes reactor criticality analysis and all of the fundamentals that go into modern calculations. Simplified one group diffusion theory models are presented and extended into sophisticated multi-group transport theory models. The second half of the book deals with the two main topics of interest related to operating reactors - reactor kinetics/dynamics, and in-core fuel management. Additional chapters have been added to expand and bring the material up-to-date and include the utilization of more computer codes. Code models and detailed data sets are provided along with example problems making this a useful text for students and researchers wishing to develop an understanding of nuclear power and its implementation in today's modern energy spectrum. Covers the fundamentals of neutronic analysis for nuclear reactor systems to help understand nuclear reactor theory; Describes the benefits, uses, safety features, and challenges related to implementation of Small Modular Reactors; Provides examples, data sets, and code to assist the reader in obtaining mastery over the subjects.

ISBN: 9783030049065

Standard No.: 10.1007/978-3-030-04906-5doiSubjects--Topical Terms:

673875
Nuclear reactors.

LC Class. No.: TK9202 / .Z648 2019

Dewey Class. No.: 621.483

Neutronic analysis for nuclear reactor systems
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245 1 0 $a Neutronic analysis for nuclear reactor systems $h [electronic resource] / $c by Bahman Zohuri.
250 $a 2nd ed.
260 $a Cham : $b Springer International Publishing : $b Imprint: Springer, $c 2019.
300 $a xxii, 663 p. : $b ill., digital ; $c 24 cm.
505 0 $a Neutron Physics Background -- Modeling Neutron Transport and Interactions -- Spatial Effects in Modeling Neutron Diffusion -- Energy effects in modeling neutron diffusion -- 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 -- Reactor Dynamics -- Reactor Stability -- Numerical Modeling for Time Dependent Problems -- Fission product buildup and decay -- Fuel burn-up and fuel management -- Why nuclear power energy -- Small Modular Reactors and their innovative designs -- Design and analysis of a nuclear reactor core for small modular reactors.
520 $a This expanded new edition develops the theory of nuclear reactors from the fundamentals of fission to the operating characteristics of modern reactors. The first half of the book emphasizes reactor criticality analysis and all of the fundamentals that go into modern calculations. Simplified one group diffusion theory models are presented and extended into sophisticated multi-group transport theory models. The second half of the book deals with the two main topics of interest related to operating reactors - reactor kinetics/dynamics, and in-core fuel management. Additional chapters have been added to expand and bring the material up-to-date and include the utilization of more computer codes. Code models and detailed data sets are provided along with example problems making this a useful text for students and researchers wishing to develop an understanding of nuclear power and its implementation in today's modern energy spectrum. Covers the fundamentals of neutronic analysis for nuclear reactor systems to help understand nuclear reactor theory; Describes the benefits, uses, safety features, and challenges related to implementation of Small Modular Reactors; Provides examples, data sets, and code to assist the reader in obtaining mastery over the subjects.
650 0 $a Nuclear reactors. $3 673875
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856 4 0 $u https://doi.org/10.1007/978-3-030-04906-5
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