This volume provides fundamentals of nuclear thermalhydraulics for reactor design and safety assessment. It also describes the basis for assessing cooling performance of nuclear reactors under accidental conditions. The descriptions in this book are virtually self-contained, beyond the assumption that readers are familiar with the introductory levels of nuclear engineering. This book helps readers understand the processes for nuclear reactor plant design and the most important factors in nuclear thermal-hydraulics.

Introduces readers at the start with the fundamentals of thermodynamics, fluid dynamics and heat transfer Supplies largely self-contained descriptions Lays the scientific foundations and then provides several exercises based on practical data

Autorentext

Dr. Hajime Akimoto received his B.S. in 1962 and PhD in 1967 in physical chemistry from Tokyo Institute of Technology. For his postdoctoral research he spent three years during 1969-71 in Department of Chemistry at University of California, Riverside, and worked on chemistry of photochemical air pollution. In 1974 he joined National Institute for Environmental Studies in Tsukuba as a head of Atmospheric Chemistry Section in Atmospheric Environment Division, and then serves as Chief of Atmospheric Environment Division and Global Environment Division. Then, he moved to Research Institute for Advanced Science and Technology at the University of Tokyo as a professor in 1993. In 2000, he joined Frontier Research Center for Global Change now under Japan Agency for Marine-Earth Science and Technology as a Director of Atmospheric Composition Research Program. After 2010 he serves as director general of Asia Center for Air Pollution Research in Niigata, Japan.

Inhalt
The First Law of Thermodynamics.- Ideal gas and steam.- Second Law of Thermodynamics.- Gas Turbine Cycles and Steam Cycles.- Fundamental Equations of Flow.- Bernoulli's Equation (Mechanics of Ideal Fluids).- Law of Momentum.- Motion of Viscous Fluid.- Laminar Flow and Turbulent Flow (The Similarity Rule).- Pressure Propagation and Critical Flow(Compressible Fluid Flow).- Two-phase Flow.- Flow Oscillations.- Reactor Heat Production.- Heat Conduction.- Convective Heat Transfer.- Boiling Heat Transfer and Critical Heat Flux.- Condensation Heat Transfer.- Radiative Heat Transfer.- Thermal Hydraulics inside the Reactor.- Reactor Thermal Design.