Faithin Omaha eBook Collection

The ADINA computer code is utilized to perform mechanical response analysis of pressurized reactor primary coolant systems subjected to postulated loss-of-coola

Nuclear reactor cooling systems are the backbone of nuclear power plants, playing a critical role in managing the immense heat generated by nuclear fission reac

A nonlinear dynamic model for a passively cooled small modular reactor (SMR) is developed. The nuclear steam supply system (NSSS) model includes representations

Nuclear Reactor Kinetics and Control highlights the application of classical control methods in the frequency space to the dynamic processes of a nuclear reacto