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Residual-heat removal system for a gas-cooled pelletised-fuel reactor

机译:气冷颗粒燃料反应堆的余热去除系统

摘要

An after-heat removal system for a nuclear reactor, especially a gas-cooled nuclear reactor in which the core is formed by a pile of spherical nuclear fuel elements, comprises an outlet in the side reflector of the reactor core which is connected to an after-heat removal system and draws the hot gases from a location within the pile, the return line from the after-heat removal system opening into the main cooling gas inlet.
机译:一种用于核反应堆,尤其是气冷核反应堆的余热去除系统,其中,堆芯由一堆球形核燃料元件形成,该反应堆的后排热系统包括在反应堆芯的侧反射器中的出口,该出口连接至尾翼。排热系统,从堆内某个位置抽出热气,从排热系统返回的回流管通向主冷却气体入口。

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