Prediction of Void Fraction in PWR Subchannel by CATHARE2 Code
, 2011 The current generation of thermal-hydraulic system codes benefits of about sixty years of experiments and forty years of development and are considered mature tools to provide best estimate description of phenomena and detailed reactor system representations. However, there are continuous needs for checking the code capabilities in representing nuclear
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Development of the Advanced Subchannel Analysis Code, Plenary Lecture
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