• 专利附录
  • 专利说明
  • 权利要求
  • 类似技术
  • 同族专利
  • 引用文献
  • 法律状态
  • 优先权
    • 专利摘要:
    Nuclide generators for preparing sterile and pyrogen-free radioactive solutions consist of a generator column which is provided with radiation shielding and connected to a container for eluting agent and has a connection to a container for eluate. The generator and the container for eluting agent are located in vessels with centering devices, wherein the generator column with its radiation shielding is located in a fixed position relative to the vessel between two centering devices and connected via a cannula to the container for eluting agent which is held in a recess of one centering device in a fixed position relative to the generator column. The other centering device has also a recess for guiding and holding the eluate container which is connected to the generator column via a cannula.
    公开号:SU828990A3
    申请号:SU782600551
    申请日:1978-03-21
    公开日:1981-05-07
    发明作者:Штрекер Хельмут
    申请人:Хехст Аг (Фирма)；
    IPC主号:
    专利说明:

    The invention relates to generators for the production of radioactive isotopes.
    To prevent the loss of radioactivity due to radioactive decay, rapidly decaying isotopes are typically obtained through an isotope generator.
    Known isotope generator, in which the column and the vessel for the eluent are connected to each other and installed in a container [1] ·
    The closest technical solution is an isotope generator containing a column with radiation protection, which is connected to the vessels for the eluent and for the eluate, and the column of the generator and the vessel for eluent are installed in the container [2].
    The disadvantage of such generators is their complex and bulky design. Consumers often have to use additional protection from lead, which makes the design as a whole more difficult and makes it difficult to work with the device.
    The purpose of the invention is the creation of a compact design of an isotope generator while maintaining its protective properties.
    This goal is achieved due to the fact that in an isotope generator for producing sterile radioisotopes containing a column with radiation protection, which is connected to the vessels for the eluent and for the eluate, the column of the generator and the vessel for the eluent are installed in the container, the column of the generator is installed between with two centering devices with recesses motionless relative to the container and through one hollow needle connected to the vessel for eluent mounted motionless relative to the column of the generator in the recess of one about the centering device, and the other hollow needle is connected to the vessel for the eluate, while the vessel for the eluate is installed in the recess of the second centering device. In addition, the centering devices have recesses for centering and fixing the hollow needles.
    For the manufacture of centering devices, metals and plastics are suitable. Especially preferred has been the use of resilient plastics, for example polypropylene.
    In FIG. 1 shows a generator prepared for transportation; in FIG.
    - the generator during elution, it is equipped with additional radiation protection.
    A vessel 1 with physiological saline solution using a hollow needle 2, preferably a double-sided hollow needle, is connected to a column of a generator 3 having circular protection from radiation 4, for example, of lead. The centering device 5 holds the eluent vessel, generator column, radiation protection and hollow needle in the correct position. The eluent vessel is installed in the recess 6 of the centering device 5. Molybdenum 99 is fixed on the alumina matrix of the generator column. A second hollow needle 7, preferably a double-sided hollow needle, is connected to the second end of the generator column. This hollow needle is held by the centering device 8 and it is closed by the protective element 9. The cover 10 closes the container 11 in which the generator is packaged for transportation. In addition, the centering devices 5 and 8 provide the correct protection position for the generator during transportation.
    To elute the generator, the lid of the container 11 is removed, the protective element of the hollow needle 9 and the evacuated vessel for the eluate 12, which is transparently protected from radiation 13 from lead glass, are removed and connected to the column of the generator 3 using the hollow needle 7. The recess 14 in the centering fixture 8 serves as a guide. An additional protection against radiation during the elution of the generator is a new lead shield 15. At the end of the elution, the vessel with the eluate 12 is removed and the protective element for the hollow needle 9 is put back on. It serves to protect against contamination and to ensure sterility.
    The proposed design of the isotope generator allows, with a small weight of radiation protection, to provide the most compact apparatus.
    权利要求:
    Claims (2)
    [1]
    preferably a double-sided hollow needle, connected to the generator column 3, which has circular protection against radiation 4, for example, from lead. The centering device 5 holds in its correct position the receptacle for the solvent, the generator column, the radiation shield and the hollow needle. The eluent vessel is installed in the recess 6 of the centering device 5. A molybdenum 99 is fixed on the matrix alumina of the generator column. A second floor, a needle 7, preferably a double-sided needle, is attached to the second end of the generator column. This hollow needle is held by the centering device 8 and it is closed by a protective element 9. The cover 10 closes the container 11 in which the generator is packed for transportation. In addition, centering devices 5 and 8 ensure the correct position of the generator protection during transport. To elute the generator, the lid of the container 11 is removed, the protective element of the hollow needle 9 and the evacuated vessel for the eluate 12, which is in the transparent protection against radiation 13 from lead glass, are removed, and the hollow needle 7 is connected to the generator 7. 14 in the centering device 8 serves as a guide. An additional protection against radiation during the elution of the generator is provided by a new lead protection 15. At the end of the elution, the vessel with eluate 12 is removed and the protective element for the hollow needle 9 is put on again. It serves as protection against contamination and to ensure sterility. The proposed construction of an isotopic generator allows, with a small weight, zapd, ity from radiation to provide the most compact apparatus. Claim 1. An isotope generator for producing sterile radioisotopes containing a radiation shielded column that is connected to vessels for eluent and eluate, the generator column and eluent vessel being installed in a container, characterized in that in order to obtain a compact structure while maintaining protective properties of the generator, the column of the generator is installed between two centering devices with depressions not connected with respect to the container and is connected with a vessel for eluent mounted fixedly relative to the generator column in the recess of the centering fixture, but by another hollow needle is connected with the vessel for the eluate, wherein the eluate container for mounted in the recess of the second centering device. 2. The isotope generator according to claim 1, characterized in that the centering devices have recesses for centering and fixing the hollow needles. Sources of information taken into account in the examination 1. US patent number 3576998, cl. 250-106, published. 1971.
    [2]
    2. For France No. 2228278, cl. G 21G 1/00, published. 1975 (prototype).
    9iLS-i
    FIG ..
    类似技术:
    公开号 | 公开日 | 专利标题
    SU828990A3|1981-05-07|Isotope generator
    US3369121A|1968-02-13|Radioactive package and container therefor
    US3655985A|1972-04-11|Radiation-shielding receptacle for a bottle for receiving a radioactive eluate
    US3156532A|1964-11-10|Yttrium-90 generator
    US4020351A|1977-04-26|Generator system
    JPS5499900A|1979-08-07|Carrying or storage vessel for radioactive substance especially* reactor fuel element being subject to radioactivity
    Richards et al.1969|Rapid determination of 99Mo in separated 99mTc
    Horlock et al.1981|The preparation of a rubidium-82 radionuclide generator
    EP0102121A1|1984-03-07|Shielding device for a reservoir comprising a radioactive material
    GB1324033A|1973-07-18|Radiation installation for medical use
    US4039835A|1977-08-02|Reloadable radioactive generator system
    US4990787A|1991-02-05|Radionuclide generator system and method for its preparation and use
    Hardell et al.1962|Precision energy determination of isomeric levels and of low-lying excited states in deformed nuclei
    CA1091039A|1980-12-09|Multiple ph alumina columns for molybdenum- 99/technetium-99m generators
    US3440423A|1969-04-22|Process for preparing sterile radioactive material of the parentdaughter type
    US3912935A|1975-10-14|Apparatus for eluting a daughter radioisotope from a parent radioisotope
    US3740558A|1973-06-19|Radioactive isotope generator of short-lived nuclides
    JPS5692484A|1981-07-27|Calibrator of detector in radiation monitoring apparatus
    Taskaev et al.1995|Extraction generator for [99mTc] sodium pertechnetate production
    US3663177A|1972-05-16|Radioactive barium-137
    Tokay et al.1985|A technique for reducing interferences in epithermal neutron activation analysis
    Sivaramakrishnan et al.1976|Preparation of high purity fission produced molybdenum-90
    GB818688A|1959-08-19|Improvements in or relating to radiological irradiation appliances
    Hontzeas et al.1971|The decay scheme of 93Y
    Amano et al.1990|Specific activity of 99m TcO 4− eluates from clinical 99 Mo/99m Tc generators
    同族专利:
    公开号 | 公开日
    AT363567B|1981-08-10|
    DE2712635A1|1978-09-28|
    ATA194478A|1981-01-15|
    FR2385190A1|1978-10-20|
    AU514357B2|1981-02-05|
    US4188539A|1980-02-12|
    AU3440678A|1979-09-27|
    CA1105154A|1981-07-14|
    IT1093903B|1985-07-26|
    IT7821442D0|1978-03-21|
    ES467976A1|1979-04-16|
    DD134159A5|1979-02-07|
    FR2385190B1|1984-05-18|
    SE7803402L|1978-09-24|
    GB1571764A|1980-07-16|
    NL7803109A|1978-09-26|
    BE865259A|1978-09-25|
    NO146844B|1982-09-13|
    IL54315A|1980-12-31|
    IE780571L|1978-09-23|
    NO146844C|1982-12-22|
    DE2712635C2|1982-04-29|
    BR7801767A|1979-01-02|
    JPS53117197A|1978-10-13|
    CH627583A5|1982-01-15|
    IE46503B1|1983-06-29|
    NO781041L|1978-09-26|
    DK128778A|1978-09-24|
    引用文献:
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    RU2644395C1|2016-12-30|2018-02-12|Федеральное государственное автономное образовательное учреждение высшего образования "Национальный исследовательский Томский политехнический университет"|Generator for obtaining sterile radioisotopes|US3156532A|1961-06-30|1964-11-10|Robert F Doering|Yttrium-90 generator|
    FR1432721A|1965-02-10|1966-03-25|Saint Gobain Techn Nouvelles|Device for the production of radio-elements|
    US3446965A|1966-08-10|1969-05-27|Mallinckrodt Chemical Works|Generation and containerization of radioisotopes|
    US3814941A|1972-10-24|1974-06-04|Squibb & Sons Inc|Loading syringe for use with radioactive solutions and other non-sterile solutions|
    US4020351A|1975-06-16|1977-04-26|Union Carbide Corporation|Generator system|
    GB1532225A|1975-08-21|1978-11-15|Radiochemical Centre Ltd|Generator of radionuclide|US4698510A|1986-01-29|1987-10-06|Halliburton Company|Multiple reservoir transportation assembly for radioactive substances, and related method|
    US4712618A|1986-01-29|1987-12-15|Halliburton Company|Multiple reservoir transportation assembly for radioactive substances, and related method|
    US6366633B1|1998-08-03|2002-04-02|Eurotope Entwicklungsgesellschaft für Isotopentechnologien mbh|Storage and dispatch container for radioactive miniature radiation sources|
    GB2382453B|2002-04-11|2004-05-19|Amersham Plc|Radioisotope generator and method of construction thereof|
    US7163031B2|2004-06-15|2007-01-16|Mallinckrodt Inc.|Automated dispensing system and associated method of use|
    EP1913602A2|2005-07-27|2008-04-23|Mallinckrodt, Inc.|Alignment adapter for use with a radioisotope generator and methods of using the same|
    CA2665193C|2006-10-06|2016-02-09|Mallinckrodt Inc.|Self-aligning radioisotope elution system|
    US9240253B2|2010-04-07|2016-01-19|Ge-Hitachi Nuclear Energy Americas Llc|Column geometry to maximize elution efficiencies for molybdenum-99|
    US8866104B2|2011-01-19|2014-10-21|Mallinckrodt Llc|Radioisotope elution system|
    US8809804B2|2011-01-19|2014-08-19|Mallinckrodt Llc|Holder and tool for radioisotope elution system|
    US9153350B2|2011-01-19|2015-10-06|Mallinckrodt Llc|Protective shroud for nuclear pharmacy generators|
    ITBO20130256A1|2013-05-24|2014-11-25|Comecer Spa|CARTRIDGE FOR A RADIOPHARMACEUTICAL, SCREENED CONTAINER FOR SUCH CARTRIDGE AND CORRESPONDING EQUIPMENT FOR INFUSION OF A RADIOPHARMACEUTICAL DOSE TO A PATIENT|
    法律状态:
    优先权:
    申请号 | 申请日 | 专利标题
    DE2712635A|DE2712635C2|1977-03-23|1977-03-23|Nuclide generator for the production of radionuclides|
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