Status and Trends of ThermalHydraulic System Codes for Nuclear Power Plants With Pressurized Water Reactors
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Graphical Abstract
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Abstract
Research and development of thermalhydraulic system codes for nuclear power plants with pressurized water reactors were analyzed on their history, status and application ranges. The important roles of bestestimate methodology, codes coupling and codes qualification were pointed out. The development models of thermal hydraulic system codes around the world provide references to China’s selfinnovation.
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