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THERMAL HYDRAULICS TEST DEVICE OF SODIUM-COOLED FAST REACTOR

机译:钠冷快堆热工水力试验装置

摘要

PURPOSE: A nuclear reactor heat flow testing instrument for a sodium-cooling faster reactor is provided to prevent accidents by properly distributing the load. CONSTITUTION: The main container body of a nuclear reactor has a cylindrical shape. An upper-inner structure (120) covers the upper part of the main container body of the nuclear reactor. The upper-inner structure is placed inside the main container body of the nuclear reactor. A head supporting member (500) supports an upper head (200). The head supporting member is placed outside the main container body of the nuclear reactor.
机译:目的:提供了一个用于钠冷却速度更快的反应堆的核反应堆热流测试仪器,以通过适当分配负荷来防止事故发生。组成:核反应堆的主体容器为圆柱形。上部内部结构(120)覆盖核反应堆的主容器主体的上部。上部内部结构放置在核反应堆的主体容器内部。头支撑构件(500)支撑上头(200)。头部支撑构件放置在核反应堆的主体容器外部。

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