Nuclear Systems Volume I : Thermal Hydraulic Fundamentals, 2nd Edition

Title: Nuclear Systems Volume I : Thermal Hydraulic Fundamentals, 2nd Edition
Author: Mujid Kazimi, Neil E. Todreas
ISBN: 1439808872 / 9781439808870
Format: Hard Cover
Pages: 1034
Publisher: Taylor & Francis
Year: 2011
Availability: Out of Stock

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Nuclear power is in the midst of a generational change - with new reactor designs, plant subsystems, fuel concepts, and other information that must be explained and explored - and after the 2011 Japan disaster, nuclear reactor technologies are, of course, front and center in the public eye.

Written by leading experts from MIT, Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, Second Edition provides an in-depth introduction to nuclear power, with a focus on thermal hydraulic design and analysis of the nuclear core. A close examination of new developments in nuclear systems, this book will help readers - particularly students - to develop the knowledge and design skills required to improve the next generation of nuclear reactors.

Includes a CD-ROM with Extensive Tables for Computation

Intended for experts and senior undergraduate/early-stage graduate students, the material addresses:

  • Different types of reactors
  • Core and plant performance measures
  • Fission energy generation and deposition
  • Conservation equations
  • Thermodynamics
  • Fluid flow
  • Heat transfer


Imparting a wealth of knowledge, including their longtime experience with the safety aspects of nuclear installations, authors Todreas and Kazimi stress the integration of fluid flow and heat transfer, various reactor types, and energy source distribution. They cover recent nuclear reactor concepts and systems, including Generation III and IV reactors, as well as new power cycles. The book features new chapter problems and examples using concept parameters, and a solutions manual is available with qualifying course adoption.

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Chapter 1 : Principal Characteristics of Power Reactors
Chapter 2 : Thermal Design Principles and Application
Chapter 3 : Reactor Energy Distribution
Chapter 4 : Transport Equations for Single-Phase Flow
Chapter 5 : Transport Equations for Two-Phase Flow
Chapter 6 : Thermodynamics of Nuclear Energy Conversion Systems : Nonflow and Steady Flow : First and Second Law Applications
Chapter 7 : Thermodynamics of Nuclear Energy Conversion Systems : Nonsteady Flow First Law Analysis
Chapter 8 : Thermal Analysis of Fuel Elements
Chapter 9 : Single-Phase Fluid Mechanics
Chapter 10 : Single-Phase Heat Transfer
Chapter 11 : Two-Phase Flow Dynamics
Chapter 12 : Pool Boiling
Chapter 13 : Flow Boiling
Chapter 14 : Single Heated Channel : Steady-State Analysis

Appendices
Appendix A : Nomenclature
Appendix B : Physical and Mathematical Constants
Appendix C : Unit Systems
Appendix D : Mathematical Tables
Appendix E : Thermodynamic Properties
Appendix F : Thermophysical Properties of Some Substances
Appendix G : Dimensionless Groups of Fluid Mechanics and Heat Transfer
Appendix H : Multiplying Prefixes
Appendix I : List of Elements
Appendix J : Square and Hexagonal Array Dimensions
Appendix K : Parameters for Typical PWR and BWR-5 Reactors