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    Thermal Striping Limits Analysis on the Cylinder With a Defect of Liquid-Cooled Nuclear Fast Reactors 

    Source: Journal of Pressure Vessel Technology:;2024:;volume( 146 ):;issue: 006:;page 61505-1
    Author(s): Yu, Mingda; Du, Juan; Shao, Xuejiao; Pu, Zhuo
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The structural safety of the cylinder in liquid-cooled fast reactors is significantly affected by high-temperature thermal striping on the cylinder wall due to the free level fluctuation. Based on the elevated-temperature ...
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