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This book is indexed in
Engineering » Energy Engineering
Nuclear Reactors
Edited by Amir Zacarias Mesquita, ISBN 978-953-51-0018-8, Hard cover, 338 pages, Publisher: InTech, Chapters published February 10, 2012 under CC BY 3.0 license
DOI: 10.5772/1919
This book presents a comprehensive review of studies in nuclear reactors technology from authors across the globe. Topics discussed in this compilation include: thermal hydraulic investigation of TRIGA type research reactor, materials testing reactor and high temperature gas-cooled reactor; the use of radiogenic lead recovered from ores as a coolant for fast reactors; decay heat in reactors and spent-fuel pools; present status of two-phase flow studies in reactor components; thermal aspects of conventional and alternative fuels in supercritical water?cooled reactor; two-phase flow coolant behavior in boiling water reactors under earthquake condition; simulation of nuclear reactors core; fuel life control in light-water reactors; methods for monitoring and controlling power in nuclear reactors; structural materials modeling for the next generation of nuclear reactors; application of the results of finite group theory in reactor physics; and the usability of vermiculite as a shield for nuclear reactor.
- Chapter 1
Experimental Investigation of Thermal Hydraulics in the IPR-R1 TRIGA Nuclear Reactor - Chapter 2
Flow Instability in Material Testing Reactors - Chapter 3
Herium-Air Exchange Flow Rate Measurement Through a Narrow Flow Path - Chapter 4
New Coolant from Lead Enriched with the Isotope Lead-208 and Possibility of Its Acquisition from Thorium Ores and Minerals for Nuclear Energy Needs - Chapter 5
Decay Heat and Nuclear Data - Chapter 6
Transport of Interfacial Area Concentration in Two-Phase Flow - Chapter 7
Thermal Aspects of Conventional and Alternative Fuels in SuperCritical Water-Cooled Reactor (SCWR) Applications - Chapter 8
Development of an Analytical Method on Water-Vapor Boiling Two-Phase Flow Characteristics in BWR Fuel Assemblies Under Earthquake Condition - Chapter 9
The Theoretical Simulation of a Model by SIMULINK for Surveying the Work and Dynamical Stability of Nuclear Reactors Cores - Chapter 10
Theory of Fuel Life Control Methods at Nuclear Power Plants (NPP) with Water-Water Energetic Reactor (WWER) - Chapter 11
Improving the Performance of the Power Monitoring Channel - Chapter 12
Multiscale Materials Modeling of Structural Materials for Next Generation Nuclear Reactors - Chapter 13
Application of Finite Symmetry Groups to Reactor Calculations - Chapter 14
Neutron Shielding Properties of Some Vermiculite-Loaded New Samples - Chapter 15
Development of 99Mo Production Technology with Solution Irradiation Method
