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    PROCESSES FOR THE RECOVERY OF URANIUM FROM WET-PROCESS PHOSPHORIC ACID USING DUAL OR SINGLE CYCLE CONTINUOUS ION EXCHANGE APPROACHES
    1.
    发明申请
    PROCESSES FOR THE RECOVERY OF URANIUM FROM WET-PROCESS PHOSPHORIC ACID USING DUAL OR SINGLE CYCLE CONTINUOUS ION EXCHANGE APPROACHES 审中-公开

    公开(公告)号：US20190078176A1

    公开(公告)日：2019-03-14

    申请号：US16101807

    申请日：2018-08-13

    Applicant: K-Technologies, Inc. ,  OCP S.A.

    Inventor： William W. Berry ,  Thomas E. Baroody ,  Driss Dhiba ,  Mounir El Mahdi

    IPC: C22B60/02 ,  C01G43/00 ,  C01B25/238 ,  C01G43/01 ,  C22C28/00 ,  B01J45/00 ,  B01J49/00 ,  B01J49/53 ,  B01J39/05 ,  B01J49/06 ,  B01J49/50 ,  C22B3/42 ,  C22B3/44

    Abstract: In alternative embodiments, the invention provides processes and methods for the recovery, removal or extracting of, and subsequent purification of uranium from a wet-process phosphoric acid using a continuous ion exchange processing approach, where the uranium is recovered from a phosphoric acid, or a phos-acid feedstock using either a dual or a single stage extraction methodology. In both cases an intermediate ammonium uranyl-tricarbonate solution is formed. In alternative embodiments, in the dual cycle approach, this solution is contacted in a second continuous ion exchange system with a strong anion exchange resin then subsequently recovered as an acidic uranyl solution that is further treated to produce an intermediate uranyl peroxide compound which is ultimately calcined to produce the final uranium oxide product. In alternative embodiments, in the single cycle case, the intermediate ammonium uranyl-tricarbonate solution is evaporated to decompose the ammonium carbonate and produce an intermediate uranium carbonate/oxide solid material. These solids are digested in an acid medium, and then processed in the same manner as the secondary regeneration solution from the dual cycle process to produce an intermediate uranyl peroxide that is calcined to produce a final uranium oxide product.

    PROCESSES FOR THE RECOVERY OF URANIUM
    3.
    发明申请
    PROCESSES FOR THE RECOVERY OF URANIUM 有权

    公开(公告)号：US20230064712A1

    公开(公告)日：2023-03-02

    申请号：US17800185

    申请日：2020-09-25

    Applicant: OCP S.A.

    Inventor： Driss Dhiba ,  Mounir El Mahdi ,  William W Berry ,  Thomas E. Baroody

    IPC: C22B60/02 ,  C22B3/42

    Abstract: The present disclosure describes a method of recovering uranium including a continuous ion exchange (CIX) process including a single cycle or a dual cycle CIX process and at least a gradient elution or resin crowding process. The present disclosure also describes an apparatus including a single cycle or dual cycle CIX system and a gradient elution and/or resin crowding system.

    Processes for the recovery of uranium from wet-process phosphoric acid using dual or single cycle continuous ion exchange approaches
    5.
    发明授权
    Processes for the recovery of uranium from wet-process phosphoric acid using dual or single cycle continuous ion exchange approaches 有权

    公开(公告)号：US11047022B2

    公开(公告)日：2021-06-29

    申请号：US16101807

    申请日：2018-08-13

    Applicant: OCP S.A.

    Inventor： William W Berry ,  Thomas E. Baroody ,  Driss Dhiba ,  Mounir El Mahdi

    IPC: C22B60/00 ,  C22B60/02 ,  B01J39/05 ,  B01J49/06 ,  B01J49/50 ,  B01J49/53 ,  C01B25/238 ,  C01G43/01 ,  C01G43/00 ,  B01J45/00 ,  B01J49/00 ,  C22B3/42 ,  C22B3/44 ,  C22C28/00

    Abstract: In alternative embodiments, the invention provides processes and methods for the recovery, removal or extracting of, and subsequent purification of uranium from a wet-process phosphoric acid using a continuous ion exchange processing approach, where the uranium is recovered from a phosphoric acid, or a phos-acid feedstock using either a dual or a single stage extraction methodology. In both cases an intermediate ammonium uranyl-tricarbonate solution is formed. In alternative embodiments, in the dual cycle approach, this solution is contacted in a second continuous ion exchange system with a strong anion exchange resin then subsequently recovered as an acidic uranyl solution that is further treated to produce an intermediate uranyl peroxide compound which is ultimately calcined to produce the final uranium oxide product. In alternative embodiments, in the single cycle case, the intermediate ammonium uranyl-tricarbonate solution is evaporated to decompose the ammonium carbonate and produce an intermediate uranium carbonate/oxide solid material. These solids are digested in an acid medium, and then processed in the same manner as the secondary regeneration solution from the dual cycle process to produce an intermediate uranyl peroxide that is calcined to produce a final uranium oxide product.

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