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

Format:

Book

Author/Creator:

Brennen, Christopher E. (Christopher Earls), 1941- author.

Language:

English

Subjects (All):

Nuclear reactors--Fluid dynamics.

Nuclear reactors.

Nuclear energy.

Physical Description:

1 online resource (xv, 155 pages) : digital, PDF file(s).

Edition:

First edition.

Place of Publication:

Cambridge : Cambridge University Press, 2016.

Language Note:

English

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.

Contents:

Mathematical nomenclature

Basic nuclear power generation

Core neutronics

Some reactor designs

Core heat transfer

Multiphase flow

Reactor multiphase flows and accidents.

Notes:

Title from publisher's bibliographic system (viewed on 05 Apr 2016).

ISBN:

1-316-68180-7

1-316-68243-9

1-5231-0213-6

1-316-49426-8

OCLC:

946585419