National Science Library of Georgia

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Thermo-hydraulics of nuclear reactors / Christopher Earls Brennen, California Institute of Technology Pasadena, California.

By: Material type: TextTextPublisher: Cambridge : Cambridge University Press, 2016Description: 1 online resource (xv, 155 pages) : digital, PDF file(s)Content type:
  • text
Media type:
  • computer
Carrier type:
  • online resource
ISBN:
  • 9781316494264 (ebook)
Subject(s): Additional physical formats: Print version: : No titleDDC classification:
  • 621.48/3 23
LOC classification:
  • TK9202 .B66 2016
Online resources:
Contents:
Mathematical nomenclature -- Basic nuclear power generation -- Core neutronics -- Some reactor designs -- Core heat transfer -- Multiphase flow -- Reactor multiphase flows and accidents.
Summary: This book provides a concise and up-to-date summary of the essential thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation. Beginning with the basic nuclear physics, it leads through technical and quantitative analyses to descriptions of both the normal operation of the various modern nuclear reactor designs and the analyses of the possible departures from normal operation. It then describes both the postulated accident scenarios and summaries of the causes for the three major nuclear power generation accidents, Three Mile Island, Chernobyl and Fukushima as well as the major improvements to reactor safety that grew out of those analyses and accidents.
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Title from publisher's bibliographic system (viewed on 05 Apr 2016).

Mathematical nomenclature -- Basic nuclear power generation -- Core neutronics -- Some reactor designs -- Core heat transfer -- Multiphase flow -- Reactor multiphase flows and accidents.

This book provides a concise and up-to-date summary of the essential thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation. Beginning with the basic nuclear physics, it leads through technical and quantitative analyses to descriptions of both the normal operation of the various modern nuclear reactor designs and the analyses of the possible departures from normal operation. It then describes both the postulated accident scenarios and summaries of the causes for the three major nuclear power generation accidents, Three Mile Island, Chernobyl and Fukushima as well as the major improvements to reactor safety that grew out of those analyses and accidents.

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