Nuclear Systems: Thermal hydraulic fundamentals
This edition builds on earlier traditions in providing broad subject-area coverage, application of theory to practical aspects of commercial nuclear power, and use of instructional objectives. Like the first edition, it focuses on what distinguishes nuclear engineering from the other engineering disciplines. However, this edition includes reorganization and overall update of descriptions of reactor designs and fuel-cycle steps, and more emphasis on reactor safety, especially related to technical and management lessons learned from the TMI-2 and Chernobyl - 4 accidents.
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Thermal Hydraulic Characteristics of Power Reactors
Thermal Design Principles
Reactor Heat Generation
17 other sections not shown
annular array assumed average axial boiling boundary Brayton cycle bubbles calculated channel cladding components condensate constant control mass control volume convection coolant core correlation critical heat flux decay heat density diameter energy equation enthalpy entropy equilibrium evaluated Example fission flow conditions flow quality fluid friction factor friction pressure fuel pin fuel rod geometry given heat transfer heat-generation rate Hence inlet interface isentropic laminar flow length linear liquid LMFBR mass flow rate mass flux momentum nuclear Nusselt obtained parameters phase pressure drop primary system Problem properties pump Rankine cycle ratio reactor region relation Reynolds number rod bundles saturated shear shown in Figure single-phase spacer steam subchannel subcooled Subcooled liquid surface Table thermal conductivity thermodynamic transient transport equations tube turbine turbulent flow two-phase flow vapor velocity viscosity void fraction volumetric wall temperature