Nuclear Systems Volume I

Thermal Hydraulic Fundamentals, Third Edition

Neil E. Todreas, Mujid S. Kazimi

• Publisher: CRC Press
• Year: 2021
• Print ISBN: 9781138492448
• eBook ISBN: 9781351030489
• Topic: Physical Sciences
• Subtopic: Energy

Nuclear Systems, Volume I: Thermal Hydraulic Fundamentals, Third Edition, provides an in-depth introduction to nuclear power, focusing on thermal hydraulic design and analysis of the nuclear core and other key nuclear plant components. The authors stress the integration of fluid flow and heat transfer as applied to all power reactor types and energy source distribution. They cover nuclear reactor concepts and systems, including GEN III+, GEN IV, and SMR reactors and new power cycles. The text includes new chapter examples and problems using concept parameters, full-color text and art, computer programs, figure slides, and a solutions manual.

FEATURES

• Rigorous coverage of nuclear power generation fundamentals
• Description and analysis of the latest nuclear power plant designs and technologies
• Extensive examples in each chapter to illustrate the analysis methods which have been presented
• New full-color art and text features to enhance the presentation of topics
• Integration of fluid flow and heat transfer as applied to single- and two-phase coolants

Readers will develop the knowledge and design skills needed to improve the next generation of nuclear reactors.

1 Principal Characteristics of Power Reactors

1.1 Introduction

This chapter presents the basic characteristics of power reactors. These characteristics, along with more detailed thermal hydraulic parameters presented in further chapters, enable the student to apply the specialized techniques presented in the remainder of the text to a range of reactor types. Water-, gas- and sodium-cooled reactor types, identified in Table 1.1, encompass the principal nuclear power reactor designs that have been employed in the world. The thermal hydraulic characteristics of these reactors are presented in Sections 1.2–1.5 as part of the description of the power cycle, primary coolant system, core and fuel assembly design of these reactor types. Three classes of advanced reactors are also presented in subsequent sections, the Generation III, III+ and IV designs. The Generation III designs are advanced water reactors that have already been brought into operation (ABWR) or are under construction (EPR). The Generation III+ designs are advanced water- and gas-cooled reactors, several of which were licensed and brought into service in the 2010 decade [9]. These Generation I, II and III+ designs are discussed in Section 1.6. The Generation IV reactors described in Section 1.7 were selected by an international road mapping process and are being pursued through an internationally coordinated research and development activity for deployment in the period 2020–2040 [10]. Figure 1.1 presents the evolution and categorization by the generation of the world’s reactor types. Tables in Chapters 1 and 2 and Appendix K provide detailed information on reactor characteristics useful for application to specific illustrative examples and homework problems in the text. Useful texts to supplement this information on power reactor characteristics are those of Knief [6] and Shultis and Faw [7].

TABLE 1.1
Basic Features of Major Power Reactor Types

Reactor Type	Neutron Spectrum	Moderator	Coolant	Fuel
				Chemical Form	Approximate Fissile Content (All ^235U Except the Sodium-Cooled Reactors)
Water-cooled	Thermal
PWR		H2O	H2O	UO2	3...

Table of contents

• Cover
• Half Title
• Title Page
• Copyright Page
• Dedication
• Table of Contents
• Preface to the Third Edition
• Preface to the First Edition
• Acknowledgments
• Authors
• 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: Applications of the First and Second Law of Thermodynamics
• 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
• Appendix A: Selected 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 Rod Array Dimensions
• Appendix K: Parameters for Typical BWR-5 and PWR Reactors
• Appendix L: Acronyms and Abbreviations
• Index