Patents by Inventor Alton Lewis Jenkins

Alton Lewis Jenkins 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).

  • Monte Carlo criticality-mode systems and methods for computing neutron and gamma fluence in a nuclear reactor
    Patent number: 7233888
    Abstract: A method for simulating three-dimensional spatial distribution of neutron and gamma fluences in a nuclear reactor includes, in an exemplary embodiment, generating a detailed geometric configuration of a nuclear reactor core and surrounding components, generating detailed fuel composition and concentration distribution, and calculating three-dimensional nuclide concentrations for the fuel rods and the water surrounding the fuel rods using the generated geometric configuration and generation fuel composition and concentration distributions. The method also includes calculating neutron and gamma fluxes using a Monte Carlo radiation transport criticality mode methodology, and generating a neutron and gamma fluence map for predetermined areas of the reactor.
    Type: Grant
    Filed: July 9, 2002
    Date of Patent: June 19, 2007
    Assignee: General Electric Company
    Inventors: Ren-Tai Chiang, Shivakumar Sitaraman, Alton Lewis Jenkins
  • Monte carlo criticality-mode systems and methods for computing neutron and gamma fluence in a nuclear reactor
    Publication number: 20040009455
    Abstract: A method for simulating three-dimensional spatial distribution of neutron and gamma fluences in a nuclear reactor includes, in an exemplary embodiment, generating a detailed geometric configuration of a nuclear reactor core and surrounding components, generating detailed fuel composition and concentration distribution, and calculating three-dimensional nuclide concentrations for the fuel rods and the water surrounding the fuel rods using the generated geometric configuration and generation fuel composition and concentration distributions. The method also includes calculating neutron and gamma fluxes using a Monte Carlo radiation transport criticality mode methodology, and generating a neutron and gamma fluence map for predetermined areas of the reactor.
    Type: Application
    Filed: July 9, 2002
    Publication date: January 15, 2004
    Inventors: Ren-Tai Chiang, Shivakumar Sitaraman, Alton Lewis Jenkins