Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, Second Edition / Edition 2

by Neil E. Todreas, Mujid S Kazimi

Overview

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.

Tables for Computation available for download at www.crcpress.com/product/ISBN/9781439808870

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.

Product Details

ISBN-13:	9781439808870
Publisher:	Taylor & Francis
Publication date:	09/21/2011
Edition description:	Older Edition
Pages:	1034
Product dimensions:	6.40(w) x 9.40(h) x 2.10(d)

About the Author

Dr. Neil Todreas is professor emeritus at MIT. He has extensive nuclear power experience, having led an industry review group on the Three Mile Island situation from 1983-1988 and served on the NRC's Reactor Safety Research Committee. In addition to his part-time teaching and research, Dr. Todreas continues to be a leading consultant to industry and government. He is a Fellow at the ASME and a member of the national academy of engineering.

Dr. Mujid Kazimi is a professor and former head of the Department of Nuclear Engineering at MIT. He also has extensive nuclear power experience, having served on the Board of Managers of the Idaho National Energy Laboratory. He is also a Fellow at the American Nuclear Society and the AAAS, and a member of the AIChE, ASME and ASEE. Dr. Kazimi has been involved with several nuclear safety studies throughout his career, covering reactor systems, as well as their fuel cycles.

Table of Contents

Principal Characteristics of Power Reactors. Thermal Design Principles and Application. Reactor Energy Distribution. Transport Equations for Single-Phase Flow. Transport Equations for Two-Phase Flow. Thermodynamics of Nuclear Energy Conversion Systems: Nonflow and Steady Flow: First and Second Law Applications. Thermodynamics of Nuclear Energy Conversion Systems: Nonsteady Flow First Law Analysis. Thermal Analysis of Fuel Elements. Approach to Simplified Flow Analysis. Single-Phase Heat Transfer. Two-Phase Flow Dynamics. Pool Boiling. Flow Boiling. Single Heated Channel: Steady-State Analysis. Appendices.