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    • 1. 发明授权
    • Dry halide method for separating the components of spent nuclear fuels
    • 用于分离乏核燃料组分的干卤法
    • US5774815A
    • 1998-06-30
    • US696187
    • 1996-08-13
    • Jerry Dale ChristianThomas Russell ThomasGlen F. Kessinger
    • Jerry Dale ChristianThomas Russell ThomasGlen F. Kessinger
    • C22B60/02G21C19/48G21F9/30G21F9/00
    • C22B60/0213G21C19/48G21F9/30G21F9/305Y02W30/884
    • The invention is a nonaqueous, single method for processing multiple spent nuclear fuel types by separating the fission- and transuranic products from the nonradioactive and fissile uranium product. The invention has four major operations: exposing the spent fuels to chlorine gas at temperatures preferably greater than 1200.degree. C. to form volatile metal chlorides; removal of the fission product chlorides, transuranic product chlorides, and any nickel chloride and chromium chloride in a molten salt scrubber at approximately 400.degree. C.; fractional condensation of the remaining volatile chlorides at temperatures ranging from 164.degree. C. to 2.degree. C.; and regeneration and recovery of the transferred spent molten salt by vacuum distillation. The residual fission products, transuranic products, and nickel- and chromium chlorides are converted to fluorides or oxides for vitrification. The method offers the significant advantages of a single, compact process that is applicable to most of the diverse nuclear fuels, minimizes secondary wastes, segregates fissile uranium from the high level wastes to resolve potential criticality concerns, segregates nonradioactive wastes from the high level wastes for volume reduction, and produces a common waste form glass or glass-ceramic.
    • 本发明是通过从非放射性和易裂变铀产物中分离裂变和超铀产物来处理多种乏燃料类型的非水单一方法。 本发明有四个主要操作:在优选大于1200℃的温度下将废燃料暴露于氯气中以形成挥发性金属氯化物; 在约400℃下在熔盐洗涤器中除去裂变产物氯化物,超铀产物氯化物和任何氯化镍和氯化铬; 剩余挥发性氯化物在164℃至2℃的温度范围内部分冷凝。 并通过真空蒸馏再生和回收转移的废熔融盐。 剩余的裂变产物,超铀产物和镍铬和铬酸盐被转化为氟化物或氧化物用于玻璃化。 该方法提供了单一,紧凑的过程的显着优点,适用于大多数不同的核燃料,最大限度地减少二次废物,将高能废物中的裂变铀分离以解决潜在的关键问题,将非放射性废物与高级废物隔离 体积减少,并产生常见的废玻璃或玻璃陶瓷。