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    PROCESS FOR RECOVERING LITHIUM PHOSPHATE AND LITHIUM SULFATE FROM LITHIUM-BEARING SILICATES
    5.
    发明申请
    PROCESS FOR RECOVERING LITHIUM PHOSPHATE AND LITHIUM SULFATE FROM LITHIUM-BEARING SILICATES 有权

    公开(公告)号：US20210222270A1

    公开(公告)日：2021-07-22

    申请号：US17059041

    申请日：2019-05-30

    申请人： LITHIUM AUSTRALIA NL ,  AUSTRALIAN NUCLEAR SCIENCE AND TECHNOLOGY ORGANISATION

    发明人： Andrew NAPIER ,  Christopher GRIFFITH

    IPC分类号： C22B26/12 ,  C01B25/30 ,  C01D15/06 ,  C01D5/02

    摘要： A process for recovering lithium phosphate and lithium sulfate from a lithium-bearing silicate is described. The process includes adding from 800 kg/t to 1600 kg/t of sulfuric acid to a slurry of the lithium-bearing silicate and from 40 kg/t to 600 kg/t of a source of fluoride to produce a leach mixture and heating said leach mixture. A lithium-bearing solution is then separated from the leach mixture and its pH is increased sequentially to pH 3.5 to 4, pH 5.5 to 6 then pH 10.5 to 11 to precipitate, respectively, a first, second and third set of impurities therefrom. The first, second and third sets of impurities are separated from the lithium-bearing solution and lime is added to maintain a soluble Ca concentration of at least 30 mg/L. The lithium-bearing solution is then softened by adding a two sequential amounts of phosphate to precipitate fluorapatite and apatite, respectively. A third amount of phosphate is added to produce a lithium phosphate precipitate which is then separated. The separated lithium phosphate precipitate is then digested in sulphuric acid to produce a digestion mixture from which a lithium sulfate precipitate is separated. An alkali metal hydroxide is added to the separated solution to produce an alkali metal phosphate solution and this is recycled for use as phosphate in the process.

    METHOD AND TARGET FOR MO-99 MANUFACTURE
    7.
    发明公开
    METHOD AND TARGET FOR MO-99 MANUFACTURE 审中-公开

    公开(公告)号：US20240127980A1

    公开(公告)日：2024-04-18

    申请号：US18263490

    申请日：2022-02-02

    申请人： Australian Nuclear Science and Technology Organisation

    发明人： Gordon James THOROGOOD ,  Robert RAPOSIO

    IPC分类号： G21G1/00 ,  G21G1/08

    CPC分类号： G21G1/001 ,  G21G1/08 ,  G21G2001/0036

    摘要： A UO2 target for use in the manufacture of 99Mo, the target comprising: a porous matrix; wherein the matrix comprises particles of UO2 or of UO2 and CeO2 with a size of less than 7.15 μm; and a molar ratio of 235U to Ce and 238U is less than 3%. The particles may comprise UO2 and the UO2 comprise uranium with a 235U to 238U ratio of less than 3% 235U enrichment. Also, a method of producing 99Mo, comprising: (a) irradiating such a UO2 target with thermal neutrons, with an irradiation time of between 3 and 7 days; then (b) extracting 99Mo from the target. The method includes performing steps (a) and (b) 2 or more times.