Method of simultaneous concentration and dilution of isotopes
    21.
    发明授权
    Method of simultaneous concentration and dilution of isotopes 失效
    同时浓缩和稀释同位素的方法

    公开(公告)号:US3953568A

    公开(公告)日:1976-04-27

    申请号:US272250

    申请日:1972-07-17

    摘要: A method of simultaneously obtaining separate enriched fractions of heavier and lighter isotopes from mixtures thereof with the use of an ion exchange resin column by passing a ligand body containing this isotope mixture through the column. The isotopes, as they are passed through the column, are present in the forms of ligand-containing coordination compounds having different valence states and are followed by an eluant and form a band which travels through the column, the front and rear portions of which are respectively enriched in one of the isotopes and depleted in the other.

    摘要翻译: 一种通过使含有该同位素混合物的配体通过该柱而使用离子交换树脂柱同时从混合物中获得较重和较轻同位素的分离的富集部分的方法。 当它们通过色谱柱时,同位素以具有不同价态的配体配位化合物的形式存在,并且随后是洗脱剂并形成行进通过柱的带,其前部和后部是 分别富集了一种同位素,另一种是耗尽的。

    Displacement chromatographic method for separating uranium isotopes
    22.
    发明授权
    Displacement chromatographic method for separating uranium isotopes 失效
    用于分离铀同位素的位移色谱方法

    公开(公告)号:US3869536A

    公开(公告)日:1975-03-04

    申请号:US8890470

    申请日:1970-11-12

    发明人: JAMES DEAN B

    IPC分类号: B01D59/30 G01N30/02 C01G43/02

    摘要: A salient part of the disclosure describes a method for separating U235 isotope from U238 isotope comprising introducing a solution containing a reducing cation such as Ti 3 into a cation-exchange resin column, thereafter introducing a uranyl solution containing both U235 and U238 isotopes, followed by introduction of a solution containing an oxidizing agent such as Fe 3 and thereafter separately recovering uranyl solutions containing uranium which is enriched in U235 isotope and uranium which is correspondingly depleted in U235 isotope.

    摘要翻译: 本公开的重要部分描述了一种从U238同位素中分离U235同位素的方法,包括将含有还原阳离子如Ti 2+的溶液引入阳离子交换树脂柱中,之后引入含有U235和U238同位素两者的铀酰溶液 ,然后引入含有Fe 3+的氧化剂的溶液,然后分别回收含有U235同位素和相当于U235同位素耗尽的铀的含有铀的铀酰溶液。

    SYSTEMS FOR SEPARATING ISOTOPES FROM A SAMPLE OF FISSION PRODUCTS

    公开(公告)号:US20210283551A1

    公开(公告)日:2021-09-16

    申请号:US17154658

    申请日:2021-01-21

    摘要: Systems and methods for efficient, effective, and safe separation and isolation of multiple isotopes (e.g., Mo, Zr, Ba, Sr, Te, and lanthanide isotopes) from fission products includes use of a plurality of chromatography columns, each containing a chromatographic resin formulated to target one or more particular isotopes. The system is operable in a “series” configuration to load the multiple columns by a single pass of the sample. Then, the system may be transitioned (e.g., using valves) to a “parallel” configuration in which multiple columns of the system may be operated simultaneously to elute targeted isotopes. Additional parallel operations of the columns, using different eluent compositions, may be used to elute different targeted isotopes. The system may be reconditioned in preparation for a subsequent sample.

    PHOTOCHEMICAL REACTOR FOR ISOTOPE SEPARATION
    26.
    发明申请

    公开(公告)号:US20200368687A1

    公开(公告)日:2020-11-26

    申请号:US16419164

    申请日:2019-05-22

    IPC分类号: B01D59/34 B01D59/30 B01D59/32

    摘要: An isotope separation method, including introducing a first reactant stream (109), containing a natural abundance of at least one desired isotopologue molecule, a second reactant stream (110), and a recycle stream (112) into a photochemical reactor (101), thus producing a raw product stream (115), introducing the raw product stream (115) into a separation device (116), thus producing at least a product stream (117), a gas filter stream (113), and the recycle stream (112), and introducing at least a portion of the gas filter stream (113) into an unconventional (gas) filter (103), wherein the product stream (117) includes the at least one desired isotopologue molecule.

    Advanced Tritium System for Separation of Tritium from Radioactive Wastes and Reactor Water in Light Water Systems
    29.
    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

    申请人: Kurion, Inc.

    IPC分类号: B01D59/30

    摘要: 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.

    摘要翻译: 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。

    Instrumentation and control scheme for implementing a boron isotopic
enrichment process
    30.
    发明授权
    Instrumentation and control scheme for implementing a boron isotopic enrichment process 失效
    实施硼同位素浓缩过程的仪器和控制方案

    公开(公告)号:US5265135A

    公开(公告)日:1993-11-23

    申请号:US960493

    申请日:1992-10-13

    CPC分类号: B01D59/30

    摘要: An apparatus for providing an inventory of an isotopically enriched acidic solution of an element that is capable of forming a water soluble weakly acidic solution at temperatures amenable to ion exchange and having a lower molecular weight isotope fraction and a higher molecular weight isotope fraction is disclosed. This apparatus includes at least two ion exchangers, each being temperature dependent with respect to their storage capacity of said lower and higher molecular weight isotopes, a hot tank containing a hot tank solution and a cold tank containing a cold tank solution both flow coupled to the ion exchangers. A first series of valves is selectively operable to direct the hot tank solution to one of the ion exchanger and to direct the cold tank solution to the other ion exchangers. A second series of valves is selectively operable to direct the flow from the ion exchangers to either the hot tank or the cold tank. An analyzer for sampling the solution is located upstream from the hot tank. The analyzer analyzes the sample to determine a content of the lower and higher molecular weight isotopes. A digital computer is connected to the analyzer for computing. a switchover signal based on a value of the actual lower molecular weight isotope enrichment flowing into the hot tank and a predicted value of the amount of the lower molecular weight isotope enrichment in the hot tank.