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RISThermal-Design Options for Pressure-Channel SCWRS With Cogeneration of Hydrogen
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Currently there are a number of Generation IV supercritical water-cooled nuclear reactor (SCWR) concepts under development worldwide. The main objectives for developing and utilizing SCWRs are (1) ...
Thermal Aspects of Uranium Carbide and Uranium Dicarbide Fuels in Supercritical Water-Cooled Nuclear Reactors
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Supercritical water-cooled nuclear reactors (SCWRs) are a Generation IV reactor concept. SCWRs will use a light-water coolant at operating parameters set above the critical point of water (22.1 ...