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Thermal-hydraulic analysis of nuclea...
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Thermal-hydraulic analysis of nuclear reactors
Record Type:
Electronic resources : Monograph/item
Title/Author:
Thermal-hydraulic analysis of nuclear reactorsby Bahman Zohuri.
Author:
Zohuri, Bahman.
Published:
Cham :Springer International Publishing :2017.
Description:
xxviii, 835 p. :ill. (some col.), digital ;24 cm.
Contained By:
Springer eBooks
Subject:
Nuclear engineering.
Online resource:
http://dx.doi.org/10.1007/978-3-319-53829-7
ISBN:
9783319538297$q(electronic bk.)
Thermal-hydraulic analysis of nuclear reactors
Zohuri, Bahman.
Thermal-hydraulic analysis of nuclear reactors
[electronic resource] /by Bahman Zohuri. - 2nd ed. - Cham :Springer International Publishing :2017. - xxviii, 835 p. :ill. (some col.), digital ;24 cm.
An Introduction to Thermal Hydraulic Aspects of Nuclear Power Reactors -- Thermodynamics -- Transport Properties -- General Conservation Equations -- Laminar Incompressible Forced Convection -- Turbulent Forced Convection -- Compressible Flow -- Conduction Heat Transfer -- Forced Convection Heat Transfer -- Natural or Free Convection -- Mass Transfer -- Thermal Radiation -- Multi-Phase Flow Dynamics -- Convective Boiling -- Thermal Stress -- Combined Cycle Driven Efficiency in Nuclear Power Plant -- Heat Exchangers -- Analysis of Reactor Accident -- Probabilistic Risk Assessment -- Nuclear Power Plants -- Nuclear Fuel Cycle -- The Economic Future of Nuclear Power -- Safety, Waste Disposal, Containment, and Accidentss -- Appendix A: Table and Graphs Compilations -- Appendix B: Physical Property Tables -- Appendix C: Units, Dimensions and Conversion Factors -- Appendix D: Physical Properties -- Appendix E: Fluid Property Data -- Appendix F: Basic Equations -- Index.
ISBN: 9783319538297$q(electronic bk.)
Standard No.: 10.1007/978-3-319-53829-7doiSubjects--Topical Terms:
265558
Nuclear engineering.
LC Class. No.: TK9145
Dewey Class. No.: 621.4831
Thermal-hydraulic analysis of nuclear reactors
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An Introduction to Thermal Hydraulic Aspects of Nuclear Power Reactors -- Thermodynamics -- Transport Properties -- General Conservation Equations -- Laminar Incompressible Forced Convection -- Turbulent Forced Convection -- Compressible Flow -- Conduction Heat Transfer -- Forced Convection Heat Transfer -- Natural or Free Convection -- Mass Transfer -- Thermal Radiation -- Multi-Phase Flow Dynamics -- Convective Boiling -- Thermal Stress -- Combined Cycle Driven Efficiency in Nuclear Power Plant -- Heat Exchangers -- Analysis of Reactor Accident -- Probabilistic Risk Assessment -- Nuclear Power Plants -- Nuclear Fuel Cycle -- The Economic Future of Nuclear Power -- Safety, Waste Disposal, Containment, and Accidentss -- Appendix A: Table and Graphs Compilations -- Appendix B: Physical Property Tables -- Appendix C: Units, Dimensions and Conversion Factors -- Appendix D: Physical Properties -- Appendix E: Fluid Property Data -- Appendix F: Basic Equations -- Index.
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based on 0 review(s)
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電子館藏
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1 records • Pages 1 •
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EB TK9145 Z85 2017
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1 records • Pages 1 •
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http://dx.doi.org/10.1007/978-3-319-53829-7
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