Thermal-Hydraulic Analysis of Nuclear Reactors

New technology plans for using a Nuclear Air-Brayton as a storage system for a low carbon grid are presented along withupdated component sizes and performance criteria for Small Modular Reactors. Written in a lucid, straight-forward style while retaining scientific rigor, the content is accessible t...

Full description

Bibliographic Details
Main Author: Zohuri, Bahman
Format: eBook
Language:English
Published: Cham Springer International Publishing 2017, 2017
Edition:2nd ed. 2017
Subjects:
Online Access:
Collection: Springer eBooks 2005- - Collection details see MPG.ReNa
LEADER 04352nmm a2200409 u 4500
001 EB001455911
003 EBX01000000000000000916781
005 00000000000000.0
007 cr|||||||||||||||||||||
008 170608 ||| eng
020 |a 9783319538297 
100 1 |a Zohuri, Bahman 
245 0 0 |a Thermal-Hydraulic Analysis of Nuclear Reactors  |h Elektronische Ressource  |c by Bahman Zohuri 
250 |a 2nd ed. 2017 
260 |a Cham  |b Springer International Publishing  |c 2017, 2017 
300 |a XXVIII, 835 p. 453 illus., 173 illus. in color  |b online resource 
505 0 |a 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 
653 |a Nuclear Energy 
653 |a Engineering Fluid Dynamics 
653 |a Fluid mechanics 
653 |a Heat engineering 
653 |a Engineering mathematics 
653 |a Thermodynamics 
653 |a Heat transfer 
653 |a Nuclear engineering 
653 |a Engineering / Data processing 
653 |a Mass transfer 
653 |a Engineering Thermodynamics, Heat and Mass Transfer 
653 |a Mathematical and Computational Engineering Applications 
041 0 7 |a eng  |2 ISO 639-2 
989 |b Springer  |a Springer eBooks 2005- 
028 5 0 |a 10.1007/978-3-319-53829-7 
856 4 0 |u https://doi.org/10.1007/978-3-319-53829-7?nosfx=y  |x Verlag  |3 Volltext 
082 0 |a 621.48 
520 |a New technology plans for using a Nuclear Air-Brayton as a storage system for a low carbon grid are presented along withupdated component sizes and performance criteria for Small Modular Reactors. Written in a lucid, straight-forward style while retaining scientific rigor, the content is accessible to upper division undergraduate students and aimed at practicing engineers in nuclear power facilities and engineering scientists and technicians in industry, academic research groups, and national laboratories. The book is also a valuable resource for students and faculty in various engineering programs concerned with nuclear reactors.  
520 |a This revised text covers the fundamentals of thermodynamics required to understand electrical power generation systems and the application of these principles to nuclear reactor power plant systems. The book begins with fundamental definitions of units and dimensions, thermodynamic variables and the Laws of Thermodynamics progressing to sections on specific applications of the Brayton and Rankine cycles for power generation and projected reactor systems design issues. It is not a traditional general thermodynamics text, per se, but a practical thermodynamics volume intended to explain the fundamentals and apply them to the challenges facing actual nuclear power plants systems, where thermal hydraulics comes to play. There have been significant new findings for intercooled systems since the previous edition published and they will be included in this volume.  
520 |a • Provides extensive coverage of thermal hydraulics with thermodynamics in nuclear reactors, from fundamentals to applications; • Reinforces fundamentals of fluid dynamics and heat transfer; thermal and hydraulic analysis of nuclear reactors, two-phase flow and boiling, compressible flow, stress analysis and energy conversion methods; • Includes detailed appendices that cover metric and English system units and conversions, detailed steam and gas tables, heat transfer properties and nuclear reactor system descriptions