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652 条记录 (耗时 0.017 秒)

    Uranium recovery
    71.
    发明授权
    Uranium recovery 失效
    铀回收

    公开(公告)号：US3743695A

    公开(公告)日：1973-07-03

    申请号：US3743695D

    申请日：1970-09-17

    申请人： US INTERIOR

    发明人： D ARCY GEORGE ,  ROSS J

    IPC分类号： C22B60/02 ,  C01G56/00

    CPC分类号： C22B60/026 ,  C22B60/0265

    摘要： THE INVENTION RELATES TO AN IMPROVED METHOD FOR RECOVERY OF URANIUM BY ELUTION FROM AN ION EXCHANGE RESIN USING SULFURIC ACID AS THE ELUTING AGENT. THE ELUTION IS CONDUCTED IN A SERIES OF STAGES, EACH ELUTION STAGE BEING COUPLED WITH A SOLVENT EXTRACTION STAGE, THEREBY ACHIEVING A SUBSTANTIALLY IMPROVED RATE OF URANIUM ELUTION.

    Method for the preparation of grains
    72.
    发明授权
    Method for the preparation of grains 失效
    制备谷物的方法

    公开(公告)号：US3717581A

    公开(公告)日：1973-02-20

    申请号：US3717581D

    申请日：1970-01-05

    申请人： REACTOR CENTRUM NEDERLAND

    发明人： NOOTHOUT A

    IPC分类号： C01G56/00 ,  B01J2/08 ,  G21C3/62 ,  B01J13/00

    CPC分类号： B01J2/08 ,  G21C3/623 ,  Y02E30/38

    摘要： A METHOD FOR PREPARING PARTICLES OF METAL HYDROXIDE GELS BY TREATING A CONCENTRATED AQUEOUS SOLUTION OF AT LEAST ONE HYDROLYZABLE METAL SALT, THE HYDROXIDE OF WHICH IS ONLY SLIGHTLY SOLUBLE IN WATER, SIMULTANEOUSLY WITH AMMONIA AND HEAT. THE SOLID SUBSTANCE THUS OBTAINED IS SEPARATED, WASHED AND HEATED THEREBY CONVERTING THE SOLID SUBSTANCE TO METAL OXIDE PARTICLES. THE HYDROLYZABLE METAL SALT STARTING MATERIALS ARE CONCENTRATED SOLUTIONS ANION-DEFICIENT METAL SALT SOLUTIONS, HAVING A RATIO OF CONJUGATED BASE TO METAL LOWER THAN THAT OF THE NORMAL SALT. WHEN A NITRATE-DEFENDANT URANYL NITRATE SOLUTION IS MIXED WIT AN AMMONIA-RELEASING AGENT, THEN DISPERSED IN A HOT PHASE IMMISCIBLE WITH THE AQUEOUS PHASE, THE RESULTING SOLIDIFICATION PRODUCES MICROSPHERES OF URANYL NITRATE, WHICH ARE USEFUL AS FUEL CELLS IN NUCLEAR REACTORS.

    Irradiated fuel recovery system
    73.
    发明授权
    Irradiated fuel recovery system 失效
    IRRADIATED燃料回收系统

    公开(公告)号：US3714324A

    公开(公告)日：1973-01-30

    申请号：US3714324D

    申请日：1968-06-18

    申请人： GEN ELECTRIC

    发明人： WEECH M

    IPC分类号： B01D11/04 ,  C01G43/00 ,  C01G56/00 ,  C01G99/00 ,  C22B60/02 ,  G21C19/46 ,  B01D11/00

    CPC分类号： G21C19/46 ,  C01G43/00 ,  C01G56/001 ,  C01G99/006 ,  C22B60/026 ,  Y02P10/212 ,  Y02W30/883

    摘要： An improved process for recovering irradiated nuclear reactor fuel material is disclosed. This process includes the steps of extracting uranium, plutonium and neptunium from a solution of irradiated fuel, passing this stream to a reflux column, where a high saturation of uranium is maintained. Separation of uranium from plutonium and neptunium, and further decontamination of uranium results from this high saturation. This process is simple, has a high recovery efficiency and high decontamination, uses relatively small amounts of process reagents and produces a relatively small volume of radioactive waste material.

    摘要翻译： 公开了一种用于回收辐照的核反应堆燃料材料的改进方法。 该方法包括从辐照燃料溶液中提取铀，钚和the the的步骤，将该物流送入回流塔，在那里保持铀饱和度高。 从钚和分离铀，进一步净化铀会导致这种高饱和度。 该方法简单，具有高回收效率和高去污性，使用相对少量的加工试剂，并产生较小体积的放射性废料。

    Method for preparing stable urania-plutonia sols
    76.
    发明授权
    Method for preparing stable urania-plutonia sols 失效
    制备稳定的尿嘧啶溶液的方法

    公开(公告)号：US3600323A

    公开(公告)日：1971-08-17

    申请号：US3600323D

    申请日：1969-10-06

    申请人： ATOMIC ENERGY COMMISSION

    发明人： TALLENT OTHAR K

    IPC分类号： B01J13/00 ,  C01G56/00 ,  C09K3/00

    CPC分类号： B01J13/0017 ,  B01J13/0047 ,  C01G56/004

    摘要： A METHOD FOR PREPARING STABLE URANIA-PLUTONIA SOLS WHICH EXHIBIT MINIMAL OXIDATION-REDUCTION BETWEEN THE TETRAVALENT IONIC SPECIES IS PROVIDED BY PREPARING A NITRATESTABILIZED POLYMERIC TETRAVALENT PLUTONIUM SOL BY ALCOHOL EXTRACTION OF A PLUTONIUM NITRATE SOLUTION, MIXING THE TETRAVALENT PLUTONIUM SOL WITH A CRYSTALLINE, NITRATESTABILIZED, TETRAVALENT URANIUM SOL AND THEREAFTER REMOVING NITRATE BY SOLVENT EXTRACTION.

    Method of obtaining americium
    77.
    发明授权
    Method of obtaining americium 失效
    获得美国的方法

    公开(公告)号：US3554867A

    公开(公告)日：1971-01-12

    申请号：US69272946

    申请日：1946-08-23

    申请人： ATOMIC ENERGY COMMISSION

    发明人： THOMPSON STANLEY G

    IPC分类号： C01G56/00 ,  C01G51/00 ,  G21G1/00

    CPC分类号： C01G56/002

    摘要： 1. IN A PROCESS FOR THE SYNTHESIS OF ELEMENT 95, THE STEPS WHICH COMPRISE DISSOLVING A NEUTRON-IRRADIATED MASS OF URANIUM CONTAINING A TRANSURANIC FRACTION COMPRISING PREDOMINANTLY PLUTONIUM WHICH CONTAINS AT LEAST ABOUT 0.01% OF THE ISOTOPE 94**241 AND A DETECTABLE QUANTITY OF ELEMENT 95 IN AN AQUEOUS ACIDIC SOLUTION, OXIDIZING THE PLUTONIUM CONTAINED IN THE RESULTING SOLUTION TO A VALENT STATE GREATER THAN +4, REMOVING URANIUM FISSION PRODUCTS AND ELEMENT 95 THEREFROM BY MEANS OF A WATER-INSOLUBLE RARE EARTH SALT CARRIER, DISSOLVING THE CARRIER PRECIPITATE THUS OBTAINED, INTRODUCING FLOUSILICATE IONS INTO THE RESULTING SOLUTION, CONTACTING SAID SOLUTION WITH A WATER-INSOLUBLE RARE EARTH SALT CARRIER FOR SAID FISSION PRODUCTS AND SEPARATING THE RESULTING PRECIPITATE, ADDING SUFFICIENT HYDROFLUORIC ACID TO RENDER THE SUPERNATANT SOLUTION THUS OBTAINED FROM ABOUT 3 TO 6 M WITH RESPECT THERETO, THEREAFTER CONTACTING THE SOLUTION WITH A WATER-INSOLUBLE RARE EARTH SALT CARRIER FOR ELEMENT 95, AND SEPARATING THE CARRIER PRECIPITATE FROM THE SOLUTION.