Patents by Inventor Hsin-Han Hsieh

Hsin-Han Hsieh has filed for patents to protect the following inventions. This listing includes patent applications that are pending as well as patents that have already been granted by the United States Patent and Trademark Office (USPTO).

  • Patent number: 9266084
    Abstract: The invention provides an automatic synthesizer apparatus and method for producing radiopharmaceutical tumor imaging agent Gallium-68-DOTATATE with one button control process to effectively isolate the medication in vials from the contamination of environment and manual operations, saving the costs of investment in production with alleviation of the critical standard required for the environmental equipments to be used for production.
    Type: Grant
    Filed: June 13, 2013
    Date of Patent: February 23, 2016
    Assignee: INSTITUTE OF NUCLEAR ENERGY RESEARCH
    Inventors: Ming-Hsin Li, Hsin-Han Hsieh
  • Patent number: 9102997
    Abstract: A method of purification for recycling of gallium-69 isotopes includes processes of proton irradiation and dissolution for a silver alloy plating target with gallium-69. After the proton irradiation and dissolution, a high concentration elution liquid of gallium-69 and germanium-68 is obtained by washing through an ion-exchange resin to filter out gallium-69 solution, followed by neutralizing precipitation, drying, and sintering treatments to obtain a gallium oxide. The gallium oxide can be dissolved to produce a solid target, and the washing processes can be repeated. The solid target after use can be placed in recycling again. This method is not only implemented to reduce the cost of production and comply with recycling notion nowadays, but also enhance efficiency in the practical application of radioisotopes.
    Type: Grant
    Filed: July 8, 2013
    Date of Patent: August 11, 2015
    Assignee: INSTITUTE OF NUCLEAR ENERGY RESEARCH
    Inventors: Ming-Hsin Li, Hsin-Han Hsieh
  • Publication number: 20150010447
    Abstract: A method of purification for recycling of gallium-69 isotopes includes processes of proton irradiation and dissolution for a silver alloy plating target with gallium-69. After the proton irradiation and dissolution, a high concentration elution liquid of gallium-69 and germanium-68 is obtained by washing through an ion-exchange resin to filter out gallium-69 solution, followed by neutralizing precipitation, drying, and sintering treatments to obtain a gallium oxide. The gallium oxide can be dissolved to produce a solid target, and the washing processes can be repeated. The solid target after use can be placed in recycling again. This method is not only implemented to reduce the cost of production and comply with recycling notion nowadays, but also enhance efficiency in the practical application of radioisotopes.
    Type: Application
    Filed: July 8, 2013
    Publication date: January 8, 2015
    Inventors: Ming-Hsin Li, Hsin-Han Hsieh