System for concentrating a moderating solution utilized in a pressurized water nuclear power plant
    1.
    发明授权
    System for concentrating a moderating solution utilized in a pressurized water nuclear power plant 失效
    用于浓缩加压水核电站的现代解决方案系统

    公开(公告)号:US3839159A

    公开(公告)日:1974-10-01

    申请号:US20339771

    申请日:1971-11-30

    CPC classification number: G21C7/22 Y02E30/32 Y02E30/39 Y10S203/19

    Abstract: A system for concentrating a solution of boric acid solution to a predetermined concentration and stripping the radioactive gases from the solution. The system is generally operable so that there is a continuous feed of weak boric acid solution and a continuous discharge of pure water from the system during the concentrating portion of the cycle and the system is operable so that when the boric acid solution reaches a predetermined concentration, the weak acid feed and pure water discharge are shut off, the pure water is recirculated through the system until the boric acid of predetermined concentration is removed to storage tanks. The system has sequentially operated controls which minimize the thermodynamic shock as the system is switched from the recycle portion of the cycle to the distillate discharge portion of the cycle.

    Abstract translation: 一种将硼酸溶液浓缩至预定浓度并从溶液中汽提放射性气体的系统。 该系统通常是可操作的,使得在循环的浓缩部分期间存在弱的硼酸溶液的连续进料和来自系统的纯水的连续排出,并且系统可操作使得当硼酸溶液达到预定浓度 ,弱酸进料和纯水排放被关闭,纯水通过系统再循环,直到预定浓度的硼酸被除去到储罐。 当系统从循环的循环部分切换到循环的馏出物排出部分时,系统具有使热力学冲击最小化的系统。

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