Nuclear Reactors
معرفی کتاب «Nuclear Reactors» نوشتهٔ Amir Zacarias Mesquita، منتشرشده توسط نشر INTECH Open Access Publisher در سال 2012. این کتاب در فرمت pdf، زبان انگلیسی ارائه شده است. «Nuclear Reactors» در دستهٔ بدون دستهبندی قرار دارد.
Preface Nuclear Reactors......Page 1 01 Experimental Investigation of Thermal Hydraulics in the IPR-R1 TRIGA Nuclear Reactor ......Page 13 02 Flow Instability in Material Testing Reactors ......Page 37 03 Herium-Air Exchange Flow Rate Measurement Through a Narrow Flow Path ......Page 59 04 New Coolant from Lead Enriched with the Isotope Lead-208 and Possibility of Its Acquisition from Thorium Ores and Minerals for Nuclear Energy Needs ......Page 69 05 Decay Heat and Nuclear Data ......Page 83 06 Transport of Interfacial Area Concentration in Two-Phase Flow ......Page 99 07 Thermal Aspects of Conventional and Alternative Fuels in SuperCritical Water-Cooled Reactor (SCWR) Applications ......Page 135 08 Development of an Analytical Method on Water-Vapor Boiling Two-Phase Flow Characteristics in BWR Fuel Assemblies Under Earthquake Condition ......Page 169 09 The Theoretical Simulation of a Model by SIMULINK for Surveying the Work and Dynamical Stability of Nuclear Reactors Cores ......Page 187 10 Theory of Fuel Life Control Methods at Nuclear Power Plants (NPP) with Water-Water Energetic Reactor (WWER) ......Page 209 11 Improving the Performance of the Power Monitoring Channel ......Page 243 12 Multiscale Materials Modeling of Structural Materials for Next Generation Nuclear Reactors ......Page 271 13 Application of Finite Symmetry Groups to Reactor Calculations ......Page 297 14 Neutron Shielding Properties of Some Vermiculite-Loaded New Samples ......Page 325 15_Inaba_final......Page 335 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
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