Patents by Inventor Dong Young Chung

Dong Young Chung 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).

  • Publication number: 20250022784
    Abstract: A method of manufacturing a semiconductor device having a semiconductor die within an extended substrate and a bottom substrate may include bonding a bottom surface of a semiconductor die to a top surface of a bottom substrate, forming an adhering member to a top surface of the semiconductor die, bonding an extended substrate to the semiconductor die and to the top surface of the bottom substrate utilizing the adhering member and a conductive bump on a bottom surface of the extended substrate and a conductive bump on the bottom substrate. The semiconductor die and the conductive bumps may be encapsulated utilizing a mold member. The conductive bump on the bottom surface of the extended substrate may be electrically connected to a terminal on the top surface of the extended substrate. The adhering member may include a laminate film, a non-conductive film adhesive, or a thermal hardening liquid adhesive.
    Type: Application
    Filed: September 27, 2024
    Publication date: January 16, 2025
    Inventors: Jae Yun Kim, Gi Tae Lim, Woon Kab Jung, Ju Hoon Yoon, Dong Joo Park, Byong Woo Cho, Gyu Wan Han, Ji Young Chung, Jin Seong Kim, Do Hyun Na
  • Patent number: 7749469
    Abstract: Disclosed is a process for recovery of uranium from a spent nuclear fuel using a carbonate solution, characterized by excellent proliferation resistance of preventing leaching of transuranium element (TRU) nuclides such as Pu, Np, Am, Cm, etc. from the spent nuclear fuel as well as environmental friendliness of minimizing waste generation, wherein a highly alkaline carbonate solution is used to separate uranium alone from the spent nuclear fuel.
    Type: Grant
    Filed: December 17, 2008
    Date of Patent: July 6, 2010
    Assignee: Korea Atomic Energy Research Institute
    Inventors: Kwang Wook Kim, Eil Hee Lee, Dong Young Chung, Han Bum Yang, Jae Kwan Lim, Kee Soo Cho, Kee Chan Song, Kyu Seok Song, Kwang Yong Jee
  • Publication number: 20090269261
    Abstract: Disclosed is a process for recovery of uranium from a spent nuclear fuel using a carbonate solution, characterized by excellent proliferation resistance of preventing leaching of transuranium element (TRU) nuclides such as Pu, Np, Am, Cm, etc. from the spent nuclear fuel as well as environmental friendliness of minimizing waste generation, wherein a highly alkaline carbonate solution is used to separate uranium alone from the spent nuclear fuel.
    Type: Application
    Filed: December 17, 2008
    Publication date: October 29, 2009
    Applicant: Korea Atomic Energy Research Institute
    Inventors: Kwang Wook KIM, Eil Hee Lee, Dong Young Chung, Han Bum Yang, Jae Kwan Lim, Kee Soo Cho, Kee Chan Song, Kyu Seok Song, Kwang Yong Jee