Advanced Tritium System for Separation of Tritium from Radioactive Wastes and Reactor Water in Light Water Systems
    1.
    发明申请
    Advanced Tritium System for Separation of Tritium from Radioactive Wastes and Reactor Water in Light Water Systems 审中-公开
    用于在轻水系统中分离氚与放射性废物和反应堆水的高级氚系统

    公开(公告)号:US20130336870A1

    公开(公告)日:2013-12-19

    申请号:US13863206

    申请日:2013-04-15

    Applicant: Kurion, Inc.

    Abstract: Systems, methods, and processes for a high throughput, low concentration processing of low activity tritiated light water include the electrolysis of at least some of the tritiated water to produce hydrogen and tritium gas. The hydrogen and tritium gas produced by electrolysis in some cases are combined with heated water vapor to increase throughput and passed through a liquid phase catalytic exchange column, which generally includes a catalyst that includes palladium coated with a hydrophobic polymer. As the hydrogen and tritium gas, along with heated water vapor, rise through the LPCE column, the tritium is retained on the catalyst. Deionized wash water passes down the column (i.e., in the opposite direction of the flow of the hydrogen gas and heated water vapor) and carries the retained tritium out of the LPCE column. Useful in separating tritium from radioactive waste materials and from the water from nuclear reactors.

    Abstract translation: 低活性氚化轻水的高通量,低浓度处理的系统,方法和方法包括至少一些氚化水的电解以产生氢和氚气。 通过电解产生的氢气和氚气在一些情况下与加热的水蒸汽结合以增加生产量并通过液相催化交换柱,其通常包括包含用疏水性聚合物涂覆的钯的催化剂。 由于氢气和氚气体以及加热的水蒸汽通过LPCE柱上升,氚保留在催化剂上。 去离子的洗涤水通过柱(即,在与氢气和加热的水蒸汽的流动的相反方向)下运送并将保留的氚输出LPCE柱。 可用于将氚与放射性废物和核反应堆的水分离。

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