NUCLEAR REACTOR THERMAL HYDRAULICS

Catalog description

Provides an in-depth examination of the thermal hydraulic behavior of nuclear reactor systems. Explores the principles of hydrodynamics and the mechanisms of conductive, convective, and radiative heat transfer within nuclear reactors. Offers a comprehensive understanding of critical heat flux and the behavior of single- and two-phase flow in different nuclear reactor configurations. Emphasizes a fundamental understanding of energy transport and fluid flow phenomena relevant to these systems. Analytically solves the general heat conduction equation and single-phase/two-phase fluid transport equations for various cases of interest in nuclear systems. Includes a special topic on the coolant options for advanced nuclear energy systems.