Patents by Inventor SCOTT B. AASE

SCOTT B. AASE 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: 12073952
    Abstract: The present invention relates generally to the field of compensation methods for nuclear reactors and, in particular to a method for fail-safe reactivity compensation in solution-type nuclear reactors. In one embodiment, the fail-safe reactivity compensation method of the present invention augments other control methods for a nuclear reactor. In still another embodiment, the fail-safe reactivity compensation method of the present invention permits one to control a nuclear reaction in a nuclear reactor through a method that does not rely on moving components into or out of a reactor core, nor does the method of the present invention rely on the constant repositioning of control rods within a nuclear reactor in order to maintain a critical state.
    Type: Grant
    Filed: June 16, 2021
    Date of Patent: August 27, 2024
    Assignee: BWXT Technical Services Group, Inc.
    Inventors: Erik T. Nygaard, Peter L. Angelo, Scott B. Aase
  • Publication number: 20210313081
    Abstract: The present invention relates generally to the field of compensation methods for nuclear reactors and, in particular to a method for fail-safe reactivity compensation in solution-type nuclear reactors. In one embodiment, the fail-safe reactivity compensation method of the present invention augments other control methods for a nuclear reactor. In still another embodiment, the fail-safe reactivity compensation method of the present invention permits one to control a nuclear reaction in a nuclear reactor through a method that does not rely on moving components into or out of a reactor core, nor does the method of the present invention rely on the constant repositioning of control rods within a nuclear reactor in order to maintain a critical state.
    Type: Application
    Filed: June 16, 2021
    Publication date: October 7, 2021
    Inventors: Erik T. Nygaard, Peter L. Angelo, Scott B. Aase
  • Patent number: 11043309
    Abstract: The present invention relates generally to the field of compensation methods for nuclear reactors and, in particular to a method for fail-safe reactivity compensation in solution-type nuclear reactors. In one embodiment, the fail-safe reactivity compensation method of the present invention augments other control methods for a nuclear reactor. In still another embodiment, the fail-safe reactivity compensation method of the present invention permits one to control a nuclear reaction in a nuclear reactor through a method that does not rely on moving components into or out of a reactor core, nor does the method of the present invention rely on the constant repositioning of control rods within a nuclear reactor in order to maintain a critical state.
    Type: Grant
    Filed: August 17, 2017
    Date of Patent: June 22, 2021
    Assignee: BWXT Technical Services Group, Inc.
    Inventors: Erik T. Nygaard, Peter L. Angelo, Scott B. Aase
  • Patent number: 9875818
    Abstract: The present invention relates generally to the field of compensation methods for nuclear reactors and, in particular to a method for fail-safe reactivity compensation in solution-type nuclear reactors. In one embodiment, the fail-safe reactivity compensation method of the present invention augments other control methods for a nuclear reactor. In still another embodiment, the fail-safe reactivity compensation method of the present invention permits one to control a nuclear reaction in a nuclear reactor through a method that does not rely on moving components into or out of a reactor core, nor does the method of the present invention rely on the constant repositioning of control rods within a nuclear reactor in order to maintain a critical state.
    Type: Grant
    Filed: October 11, 2012
    Date of Patent: January 23, 2018
    Assignee: BWX Technologies, Inc.
    Inventors: Erik T Nygaard, Peter L Angelo, Scott B Aase
  • Publication number: 20170372804
    Abstract: The present invention relates generally to the field of compensation methods for nuclear reactors and, in particular to a method for fail-safe reactivity compensation in solution-type nuclear reactors. In one embodiment, the fail-safe reactivity compensation method of the present invention augments other control methods for a nuclear reactor. In still another embodiment, the fail-safe reactivity compensation method of the present invention permits one to control a nuclear reaction in a nuclear reactor through a method that does not rely on moving components into or out of a reactor core, nor does the method of the present invention rely on the constant repositioning of control rods within a nuclear reactor in order to maintain a critical state.
    Type: Application
    Filed: August 17, 2017
    Publication date: December 28, 2017
    Inventors: Erik T. Nygaard, Peter L. Angelo, Scott B. Aase
  • Patent number: 9475706
    Abstract: The present invention relates generally to the field of medical isotope production by fission of uranium-235 and the fuel utilized therein (e.g., the production of suitable Low Enriched Uranium (LEU is uranium having 20 weight percent or less uranium-235) fuel for medical isotope production) and, in particular to a method for producing LEU fuel and a LEU fuel product that is suitable for use in the production of medical isotopes. In one embodiment, the LEU fuel of the present invention is designed to be utilized in an Aqueous Homogeneous Reactor (AHR) for the production of various medical isotopes including, but not limited to, molybdenum-99, cesium-137, iodine-131, strontium-89, xenon-133 and yttrium-90.
    Type: Grant
    Filed: October 24, 2012
    Date of Patent: October 25, 2016
    Assignee: BWXT Technical Services Group, Inc.
    Inventors: Timothy A Policke, Scott B Aase, William R Stagg
  • Publication number: 20140112428
    Abstract: The present invention relates generally to the field of cooling systems and/or methods for cooling a heated, fissioning, or exothermic solution. In one embodiment, the present invention relates to a cooling system, and method of utilizing same, for cooling a heated, fissioning, or exothermic solution that utilizes submerged cooling coils where the system of the present invention relies on a combination of multiple factors to achieve the desired effect. In one embodiment, the present invention relates to a cooling system, and method of utilizing same, for cooling a heated, fissioning, or exothermic solution that utilizes submerged cooling coils where the system of the present invention relies on the combination of: (i) cooling coil geometry; (ii) cooling coil location and design; and (iii) cooling coil operational pressure.
    Type: Application
    Filed: October 24, 2012
    Publication date: April 24, 2014
    Applicant: BABCOCK & WILCOX TECHNICAL SERVICES GROUP, INC.
    Inventors: Timothy A. Policke, Erik T. Nygaard, Scott B. Aase
  • Publication number: 20140112858
    Abstract: The present invention relates generally to the field of medical isotope production by fission of uranium-235 and the fuel utilized therein (e.g., the production of suitable Low Enriched Uranium (LEU is uranium having 20 weight percent or less uranium-235) fuel for medical isotope production) and, in particular to a method for producing LEU fuel and a LEU fuel product that is suitable for use in the production of medical isotopes. In one embodiment, the LEU fuel of the present invention is designed to be utilized in an Aqueous Homogeneous Reactor (AHR) for the production of various medical isotopes including, but not limited to, molybdenum-99, cesium-137, iodine-131, strontium-89, xenon-133 and yttrium-90.
    Type: Application
    Filed: October 24, 2012
    Publication date: April 24, 2014
    Applicant: BABCOCK & WILCOX TECHNICAL SERVICES GROUP, INC.
    Inventors: Timothy A. Policke, Scott B. Aase, William R. Stagg
  • Publication number: 20140105349
    Abstract: The present invention relates generally to the field of compensation methods for nuclear reactors and, in particular to a method for fail-safe reactivity compensation in solution-type nuclear reactors. In one embodiment, the fail-safe reactivity compensation method of the present invention augments other control methods for a nuclear reactor. In still another embodiment, the fail-safe reactivity compensation method of the present invention permits one to control a nuclear reaction in a nuclear reactor through a method that does not rely on moving components into or out of a reactor core, nor does the method of the present invention rely on the constant repositioning of control rods within a nuclear reactor in order to maintain a critical state.
    Type: Application
    Filed: October 11, 2012
    Publication date: April 17, 2014
    Applicant: BABCOCK & WILCOX TECHNICAL SERVICES GROUP, INC.
    Inventors: Erik T. Nygaard, Peter L. Angelo, Scott B. Aase
  • Patent number: 8449850
    Abstract: A method for the extraction and purification of molybdenum, the method comprising the steps of: transferring an irradiated fuel solution to an extraction system, the irradiated fuel solution comprising iodine and molybdenum and other fission products, the extraction system comprising at least one sorbent column; passing the irradiated fuel solution upwards through the at least one sorbent-containing extraction column; directing the irradiated fuel solution towards a fuel management system by means of at least one discharge alignment valve; directing the extraction column eluate towards an iodine removal system; removing the iodine from the extraction column eluate; purifying the extraction column eluate; and collecting the purified eluate. Also disclosed is an apparatus for accomplishing the aforementioned method.
    Type: Grant
    Filed: February 17, 2011
    Date of Patent: May 28, 2013
    Assignee: Babcock & Wilcox Technical Services Group, Inc.
    Inventors: Daniel E. Glenn, Scott B. Aase, William R. Stagg
  • Publication number: 20110206579
    Abstract: A method for the extraction and purification of molybdenum, the method comprising the steps of: transferring an irradiated fuel solution to an extraction system, the irradiated fuel solution comprising iodine and molybdenum and other fission products, the extraction system comprising at least one sorbent column; passing the irradiated fuel solution upwards through the at least one sorbent-containing extraction column; directing the irradiated fuel solution towards a fuel management system by means of at least one discharge alignment valve; directing the extraction column eluate towards an iodine removal system; removing the iodine from the extraction column eluate; purifying the extraction column eluate; and collecting the purified eluate. Also disclosed is an apparatus for accomplishing the aforementioned method.
    Type: Application
    Filed: February 17, 2011
    Publication date: August 25, 2011
    Inventors: DANIEL E. GLENN, SCOTT B. AASE, WILLIAM R. STAGG