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Nuclear Reactor Thermal Hydraulics

Author: Robert E Masterson
Publisher: Boca Raton : CRC Press LLC, 2019.
Edition/Format:   eBook : Document : 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 considerations. 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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Genre/Form: Electronic books
Additional Physical Format: Print version:
Masterson, Robert E.
Nuclear Reactor Thermal Hydraulics.
Milton : CRC Press LLC, ©2019
Material Type: Document, Internet resource
Document Type: Internet Resource, Computer File
All Authors / Contributors: Robert E Masterson
ISBN: 9781351849524 1351849522 9781315226231 1315226235 9781351849517 1351849514 9781351849500 1351849506
OCLC Number: 1113885673
Description: 1 online resource (1391 pages)
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.

Abstract:

Nuclear Thermal-Hydraulic Systems provides a comprehensive approach to nuclear reactor thermal-hydraulics, reflecting the latest technologies, reactor designs, and safety considerations. 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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