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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.
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