"The book is a comprehensive introduction to centrifugal pumps used in sodium-cooled fast reactors. It discusses the special attributes of centrifugal pumps, design features, manufacturing requirements, instrumentation, and operating experience. It covers the characteristics of mechanical pumps, used as the main coolant pumps in fast reactors"--

This comprehensive introduction to centrifugal pumps used in sodiumcooled fast reactors discusses the special attributes of centrifugal pumps, design features, manufacturing requirements, instrumentation, and operating experience. It covers the characteristics of mechanical pumps, used as the main coolant pumps in fast reactors. Key Features: Covers description of pumps in various reactors highlighting the special features of the pumps and providing an overview of futuristic design concepts Discusses the aspects related to the design, manufacture, testing, instrumentation, and operating experience of centrifugal sodium pumps Highlights the challenges in centrifugal sodium pump testing Presents topics such as cavitation testing for critical applications and thermodynamic effect on pump cavitation Real-life case studies are included for better understanding This book gives a detailed overview of the design, manufacture, testing, and operating experience of the main coolant pumps used in sodium-cooled nuclear reactors. It further discusses the special type of pumps used in fast reactor power plants to circulate liquid sodium through the core. The text examines the challenges in centrifugal sodium pump testing and types of test facilities around the world. Real-life examples are used to highlight important aspects. It is primarily written for senior undergraduate, graduate students, and academic researchers in the fields such as mechanical engineering, nuclear engineering, and chemical engineering.

Presents a survey of worldwide experience gained with fast breeder reactor design, development and operation. Coverage includes state of the art of liquid metal fast reactor development; lead-bismuth cooled (LBC) ship reactor operation experience and LBC fast power reactor development; and treatment and disposal of spent sodium.

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.