Dynamic Simulation of Sodium Cooled Fast Reactors

The text comprehensively discusses basis of mathematical modelling of the heat transfer process in a fast reactor cooled by sodium in a single volume. The text will be helpful for senior undergraduate, graduate students and academic researchers in the fields of nuclear engineering, mechanical engineering, and power cycle engineering.

Dr G.Vaidyanathan, B.E., MBA, PhD served the Department of Atomic Energy, India over a period of 38 years until 2010. As a group director of the Fast Reactor Technology group at the Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam, which is devoted to the development of Fast Reactors in India. He is a specialist in numerical and experimental thermal hydraulics and safety analysis. He was one of the key persons involved in the design and development of the experimental Fast Breeder Test Reactor (FBTR) and the Prototype Fast Breeder Reactor (PFBR) in India. He has contributed to the inhouse development of thermal hydraulic computer codes and during commissioning tests in FBTR the predictions of these codes were substantiated.

After 2010 Dr Vaidyanathan has been teaching nuclear energy and alternative systems in the Indian universities. He has brought out 4 books on nuclear energy. These books have been welcomed by many professors teaching nuclear subjects in in Indian and Foreign universities. He has developed a video module comprising of 30 lectures on nuclear reactors and safety under the NPTEL program of IIT & IISc and these have been extensively used.

Dr Vaidyanathan is a life fellow of the Institution of Engineers India, life member f the Indian nuclear society and Indian society of heat & mass transfer. He has 37 journal publications to his credit. He continues to contribute to the department as a member of the sodium safety panel (SSP) at IGCAR and the Advisory Committees for Safety review of various Projects (ACPSR) at the Atomic Energy Regulatory Board, India.