Nuclear Reactor Thermal Hydraulics

795

Nayak, Vaidyanathan

ISBN: 9789391549800

Copyright Year: 2023

Pages: 586 pp

Binding: Papeback

Publisher: Yes Dee Publishing

Out of stock

SKU: 9789391549800 Categories: ,

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.

Additional information

Weight 0.6 kg
Dimensions 23 × 21 × 2 cm

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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