Springer Japan, 2016. — 464 p. — (An Advanced Course in Nuclear Engineering. Book 4) — ISBN: 4431556028
This volume provides fundamentals of nuclear thermal–hydraulics 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.
ThermodynamicsThe First Law of Thermodynamics
Ideal Gas and Steam
Second Law of Thermodynamics
Gas Turbine Cycles and Steam Cycles
Fluid DynamicsFundamental Equations of Flow
Bernoulli’s Equation (Mechanics of Ideal Fluids)
Law of Momentum
Hydrodynamics of Viscous Fluid
Laminar Flow and Turbulent Flow (The Similarity Rule)
Pressure Propagation and Critical Flow (Compressible Fluid Flow)
Two-Phase Flow
Flow Oscillations
Heat TransferReactor 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