Thermo-Hydraulics of Nuclear Reactors

This book provides a concise summary of the essential thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation.

Christopher Earls Brennen (Author)

9781107139602, Cambridge University Press

Hardback, published 13 April 2016

160 pages, 76 b/w illus. 2 maps 1 table
26.1 x 18.2 x 1.6 cm, 0.55 kg

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.

1. Introduction
2. Basic nuclear power generation
3. CORE neutronics
4. Some reactor designs
5. Core heat transfer
6. Multiphase flow
7. Reactor multiphase flows and accidents.

Subject Areas: Mechanics of fluids [TGMF], Mechanics of solids [TGMD], Industrial chemistry & manufacturing technologies [TD], Particle & high-energy physics [PHP], Nuclear physics [PHN], Energy [PHDY], Fluid mechanics [PHDF]