Applied reactor technology and nuclear safety chapter 9 9 thermal hydraulic design of nuclear reactor cores an important aspect of nuclear reactor core analysis involves the determination of the optimal coolant flow distribution and pressure drop across the core on the one hand. O reinforces fundamentals of fluid dynamics and heat transfer thermal and hydraulic analysis of nuclear reactors two phase flow and boiling compressible flow stress analysis and energy conversion methods o includes detailed appendices that cover metric and english system units and. Provides extensive coverage of thermal hydraulics with thermodynamics in nuclear reactors beginning with fundamental definitions of units and dimensions thermodynamic variables and the laws of thermodynamics progressing to sections on specific applications of the brayton and rankine cycles for power generation and projected reactor systems design issues. Chapter 7 thermal hydraulic analysis the coolant in the pressure tube of the candu nuclear reactor core removes the thermal energy produced in the nuclear fuel the rate and form of energy transfer from the nuclear fuel through the cladding and to the coolant is strongly depend ent upon the local thermal and hydraulic conditions. A wide variety of nuclear reactor thermal hydraulic problems have been investigated at oregon state university these include the development of a library of best estimate thermal hydraulic computer codes for nuclear reactor safety analysis experimental studies of the mixing of reactor fluids in reactor relevant geometries experimental studies to characterize a variety of two phase flow
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