Thermo-Hydraulics of Nuclear Reactors
Thermo-Hydraulics of Nuclear Reactors
Christopher Earls Brennen, California Institute of Technology
No date available
Hardback
9781107139602
Hardback
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.
- A concise summary of some of the essential analyses and design principles of nuclear reactors for electricity generation
- An effective guide to the thermo-hydraulics of nuclear reactors at the graduate or advanced undergraduate level
- Provides support for advanced technical courses on nuclear power generation
Product details
No date availableHardback
9781107139602
160 pages
261 × 182 × 16 mm
0.55kg
76 b/w illus. 2 maps 1 table
Table of Contents
- 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.
