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Nuclear reactor thermal hydraulics

Author: Robert Masterson
Publisher: Boca Raton : CRC Press, [2019]
Edition/Format:   Print book : EnglishView all editions and formats
Summary:
"Nuclear Thermal-Hydraulic Systems provides a comprehensive approach to nuclear reactor thermal-hydraulics, reflecting the latest technologies, reactor designs, and safety considertions. The text makes extensive use of color images, internet links, computer graphics, and other innovative techniques to explore nuclear power plant design and operation. Key fluid mechanics, heat transfer, and nuclear engineering  Read more...
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Document Type: Book
All Authors / Contributors: Robert Masterson
ISBN: 9781138035379 1138035378
OCLC Number: 1081371626
Description: pages cm
Contents: The nuclear power industry in the world today --
The pressurized water reactor --
The boiling water reactor --
Fast reactors, gas reactors, and military reactors --
Thermal energy production in nuclear power plants --
The laws of thermodynamics --
Thermodynamic properties and equations of state --
The nuclear steam supply system --
Reactor thermal cycles --
The laws of heat transfer --
Heat removal from nuclear fuel rods --
Time dependent nuclear heat transfer --
Nuclear reactor fluid mechanics --
Fluid statics and fluid dynamics --
The conservation equations of fluid mechanics --
Single phase flow in nuclear power plants --
Laminar and turbulent flow with friction --
Core and fuel assembly fluid flow --
Reactor coolants, coolant pumps, and power turbines --
Single phase nuclear heat transfer --
Correlations for single phase nuclear heat transfer --
Natural convection in nuclear power plants --
Fundamentals of two phase flow in nuclear power plants --
Two phase nuclear heat transfer --
Heat transfer correlations for advanced two phase nuclear heat transfer --
Core temperature fields --
Nuclear hot channel factors, the critical heat flux, and the dnbr --
Thermal design limits, operating limits, and safety limits --
Equilibrium and non-equilibrium flows, critical flow, and choke flow --
Reactor accidents, dbas, and locas --
Flow oscillations, density waves, and hydrodynamic instabilities --
Containment buildings and their function --
particle transport and entrainment during reactor accidents --
Response of a containment building to a reactor LOCA.
Responsibility: Robert Masterson.

Abstract:

"Nuclear Thermal-Hydraulic Systems provides a comprehensive approach to nuclear reactor thermal-hydraulics, reflecting the latest technologies, reactor designs, and safety considertions. The text makes extensive use of color images, internet links, computer graphics, and other innovative techniques to explore nuclear power plant design and operation. Key fluid mechanics, heat transfer, and nuclear engineering concepts are carefully explained, and supported with worked examples, tables, and graphics. Intended for use in one or two semester courses, the text is suitable for both undergraduate and graduate students. A complete Solutions Manual is available for professors adopting the text"--

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