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    PURIFICATION PROCESS
    1.
    发明申请
    PURIFICATION PROCESS 审中-公开

    公开(公告)号：US20180142326A1

    公开(公告)日：2018-05-24

    申请号：US15826280

    申请日：2017-11-29

    申请人： Mallinckrodt Nuclear Medicine LLC

    发明人： Luis A.M.M. Barbosa

    IPC分类号： C22B34/34 ,  G21G1/00

    CPC分类号： C22B34/34 ,  G21G1/001 ,  G21G2001/0036

    摘要： A process for purifying Mo-99 from an acidic solution obtained by dissolving an irradiated solid target comprising uranium in an acidic medium, or from an acidic solution comprising uranium and which has previously been irradiated in a nuclear reactor, or from an acidic solution comprising uranium and which has been used as reactor fuel in a homogeneous reactor, the process comprising contacting the acidic solution with an adsorbent comprising a zirconium oxide, zirconium hydroxide, zirconium alkoxide, zirconium halide and/or zirconium oxide halide, and eluting the Mo-99 from the adsorbent using a solution of a strong base, the eluate then being subjected to a subsequent purification process involving an alkaline-based Mo-99 chromatographic recovery step on an anion exchange material. Also provided is apparatus for carrying out the process.

    Target-fueled nuclear reactor for medical isotope production
    2.
    发明授权
    Target-fueled nuclear reactor for medical isotope production 有权

    公开(公告)号：US09691511B1

    公开(公告)日：2017-06-27

    申请号：US12845497

    申请日：2010-07-28

    申请人： Richard L. Coats ,  Edward J. Parma

    发明人： Richard L. Coats ,  Edward J. Parma

    IPC分类号： G21G1/02

    CPC分类号： G21G1/02 ,  G21G1/08 ,  G21G2001/0036

    摘要： A small, low-enriched, passively safe, low-power nuclear reactor comprises a core of target and fuel pins that can be processed to produce the medical isotope 99Mo and other fission product isotopes. The fuel for the reactor and the targets for the 99Mo production are the same. The fuel can be low enriched uranium oxide, enriched to less than 20% 235U. The reactor power level can be 1 to 2 MW. The reactor is passively safe and maintains negative reactivity coefficients. The total radionuclide inventory in the reactor core is minimized since the fuel/target pins are removed and processed after 7 to 21 days.

    System and method for generating molybdenum-99 and metastable technetium-99, and other isotopes
    4.
    发明授权
    System and method for generating molybdenum-99 and metastable technetium-99, and other isotopes 有权

    公开(公告)号：US09196388B2

    公开(公告)日：2015-11-24

    申请号：US12928227

    申请日：2010-12-07

    申请人： James E. Clayton

    发明人： James E. Clayton

    IPC分类号： G21G1/00 ,  G21G1/02 ,  G21G1/10

    CPC分类号： G21G1/0005 ,  G21G1/001 ,  G21G1/02 ,  G21G1/06 ,  G21G1/10 ,  G21G1/12 ,  G21G2001/0036 ,  G21G2001/0042

    摘要： An accelerator based systems are disclosed for the generation of isotopes, such as molybdenum-98 (“99Mo”) and metastable technetium-99 (“99mTc”) from molybdenum-98 (“98Mo”). Multilayer targets are disclosed for use in the system and other systems to generate 99mTc and 98Mo, and other isotopes. In one example a multilayer target comprises a first, inner target of 98Mo surrounded, at least in part, by a separate, second outer layer of 98Mo. In another example, a first target layer of molybdenum-100 is surrounded, at least in part, by a second target layer of 98Mo. In another example, a first inner target comprises a Bremsstrahlung target material surrounded, at least in part, by a second target layer of molybdenum-100, surrounded, at least in part, by a third target layer of 98Mo.

    Technetium-99m generator system
    8.
    发明授权
    Technetium-99m generator system 失效
    锝-99m发电机系统

    公开(公告)号：US5774782A

    公开(公告)日：1998-06-30

    申请号：US619376

    申请日：1996-05-22

    申请人： Saed Mirzadeh ,  Furn F. Knapp, Jr. ,  Emory D. Collins

    发明人： Saed Mirzadeh ,  Furn F. Knapp, Jr. ,  Emory D. Collins

    IPC分类号： G21G4/08 ,  A61K51/12 ,  B01D15/04 ,  B01D59/24 ,  B01J41/04 ,  C01G99/00 ,  C07F13/00 ,  C01G57/00

    CPC分类号： A61K51/1282 ,  G21G2001/0036

    摘要： A .sup.99 Mo/.sup.99m Tc generator system includes a sorbent column loaded with a composition containing .sup.99 Mo. The sorbent column has an effluent end in fluid communication with an anion-exchange column for concentrating .sup.99m Tc eluted from the sorbent column. A method of preparing a concentrated solution of .sup.99m Tc includes the general steps of: a. providing a sorbent column loaded with a composition containing .sup.99 Mo, the sorbent column having an effluent end in fluid communication with an anion-exchange column; b. eluting the sorbent column with a salt solution to elute .sup.99m Tc from the sorbent and to trap and concentrate the eluted .sup.99m Tc on the ion-exchange column; and c. eluting the concentrated .sup.99m Tc from the ion-exchange column with a solution comprising a reductive complexing agent.

    摘要翻译： 99Mo / 99mTc发生器系统包括装载有含有99Mo的组合物的吸附塔。 吸附塔具有与阴离子交换柱流体连通的流出物末端，用于浓缩从吸附塔洗脱的99mTc。 制备99mTc浓缩溶液的方法包括以下步骤：a。 提供负载有含有99Mo的组合物的吸附剂柱，吸附塔具有与阴离子交换柱流体连通的流出物末端; b。 用盐溶液洗脱吸附剂柱，从吸附剂中洗脱99mTc，并将洗脱的99mTc捕集并浓缩在离子交换柱上; 和c。 用含有还原络合剂的溶液从离子交换柱洗脱浓缩的99mTc。

    Productions of radioisotopes
    10.
    发明授权
    Productions of radioisotopes 有权

    公开(公告)号：US11854711B2

    公开(公告)日：2023-12-26

    申请号：US17183126

    申请日：2021-02-23

    申请人： Gary M Sandquist

    发明人： Gary M Sandquist

    IPC分类号： G21G1/00 ,  G21G1/06

    CPC分类号： G21G1/001 ,  G21G1/06 ,  G21G2001/0036

    摘要： The present disclosure generally relates to methods and structures for the production of radioisotopes from the thermal neutron irradiation of selected natural isotopes. The methods, structures and operations are applicable to the production of any radioisotope that may be produced from neutron irradiation.