Description
Thermal Hydraulics is one of the important disciplines to harness the nuclear energy for conversion to electrical power, hydrogen generation, desalination, district heating, etc. This textbook is intended to be an introduction to various thermal-hydraulic topics for students of energy engineering and applied sciences as well as for professional working in the field of nuclear engineering.
It covers the fundamentals and applications of fluid flow and heat transfer to nuclear reactors design and safety with special emphasis on Pressurised Heavy Water Reactors (PHWR) and Sodium-cooled Fast Reactors (SFR). The book also addresses the issues related to passive safety features for advanced nuclear reactors. With Computational Fluid Dynamics (CFD) becoming an important tool for thermal-hydraulic analysis of nuclear reactors, the book also introduces the reader to the fundamentals of CFD.
Table of Contents
Chapter 1 Introduction to Nuclear Reactor Thermal Hydraulics
Chapter 2 Heat Generation and Reactor Kinetics
Chapter 3 Fundamentals of Nuclear Reactor Safety
Chapter 4 Fundamentals of Single-Phase Fluid Flow and Heat Transfer
Chapter 5 Fundamentals of Two-Phase Flow and Heat Transfer
Chapter 6 Fuel Element Heat Transfer
Chapter 7 Heat and Fluid Flow in Reactor Components
Chapter 8 Numerical Methods in Fluid Flow and Heat Transfer
Chapter 9 Thermal Hydraulic Analysis of PHWRs
Chapter 10 Transient Analysis of Fast Reactors
Chapter 11 Thermal Hydraulics of Advanced Reactors
Annexure A
Annexure B
Annexure C
Index
About the Author
Homi Bhabha National Institute, an Indian Deemed University established by the Department of Atomic Energy, nurtures in-depth capabilities in Nuclear Science and Engineering and serves as a catalyst to accelerate the pace of basic research and facilitate its translation into technology development and applications through academic programs.
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