Dynamic Simulation of Sodium Cooled Fast Reactors by Vaidyanathan, G.

Dynamic Simulation of Sodium Cooled Fast Reactors (Hardcover) (ISBN-13: 9781032254357)

Vendor: G. Vaidyanathan
Product type: Books
Format: Hardcover
$160.00
$160.00
$160.00
Subtotal: $160.00
Dynamic Simulation of Sodium Cooled Fast Reactors by Vaidyanathan, G.

Dynamic Simulation of Sodium Cooled Fast Reactors

$160.00
Dynamic Simulation of Sodium Cooled Fast Reactors by Vaidyanathan, G.

Dynamic Simulation of Sodium Cooled Fast Reactors

$160.00
Format: Hardcover
Description
Description
x

This book provides the basis of simulating a nuclear plant, in understanding the knowledge of how such simulations help in assuring the safety of the plants, thereby protecting the public from accidents. It provides the reader with an in-depth knowledge about modeling the thermal and flow processes in a fast reactor and gives an idea about the different numerical solution methods. The text highlights the application of the simulation to typical sodium-cooled fast reactor.

The book

- Discusses mathematical modeling of the heat transfer process in a fast reactor cooled by sodium.

- Compares different numerical techniques and brings out the best one for the solution of the models.

- Provides a methodology of validation based on experiments.

- Examines modeling and simulation aspects necessary for the safe design of a fast reactor.

- Emphasizes plant dynamics aspects, which is important for relating the interaction between the components in the heat transport systems.

- Discusses the application of the models to the design of a sodium-cooled fast reactor

It will serve as an ideal reference text for senior undergraduate, graduate students, and academic researchers in the fields of nuclear engineering, mechanical engineering, and power cycle engineering.



Author: G. Vaidyanathan
ISBN-10: 1032254351
ISBN-13: 9781032254357
Publisher: CRC Press
Language: English
Published: 11/18/2022
Pages: 256
Format: Hardcover
Weight: 1.23lbs
Size: 9.21h x 6.14w x 0.63d
By G. Vaidyanathan
By G. Vaidyanathan
x

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.

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