InTech-Ch3 Herium Air Exchange Flow Rate Measurement Through a Narrow Flow Path

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Combined Gas & Steam Turbine Power Plants

InTech-Ch1 Experimental Investigation of Thermal Hydraulics in the Ipr r1 Triga Nuclear Reactor

InTech-Ch4 New Coolant From Lead Enriched With the Isotope Lead 208 and Possibility of Its Acquisition From Thorium Ores and Minerals for Nuclear Energy Needs

InTech-Ch5 Decay Heat and Nuclear Data

InTech-Ch7 Thermal Aspects of Conventional and Alternative Fuels in Supercritical Water Cooled Reactor Scwr Applications

InTech-Ch9 the Theoretical Simulation of a Model by Simulink for Surveying the Work and Dynamical Stability of Nuclear Reactors Cores

InTech-Ch14 Neutron Shielding Properties of Some Vermiculite Loaded New Samples

InTech-Ch2 Flow Instability in Material Testing Reactors

InTech-Ch6 Transport of Interfacial Area Concentration in Two Phase Flow

InTech-Ch8 Development of an Analytical Method on Water Vapor Boiling Two Phase Flow Characteristics in Bwr Fuel Assemblies Under Earthquake Condition

InTech-Ch10 Theory of Fuel Life Control Methods at Nuclear Power Plants Npp With Water Water Energetic Reactor Wwer

InTech-Ch11 Improving the Performance of the Power Monitoring Channel

InTech-Ch12 Multiscale Materials Modeling of Structural Materials for Next Generation Nuclear Reactors

InTech-Ch13 Application of Finite Symmetry Groups to Reactor Calculations

InTech-Ch15 Development of 99mo Production Technology With Solution Irradiation Method