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).
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Patent number: 12073952Abstract: 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: GrantFiled: June 16, 2021Date of Patent: August 27, 2024Assignee: BWXT Technical Services Group, Inc.Inventors: Erik T. Nygaard, Peter L. Angelo, Scott B. Aase
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Publication number: 20210313081Abstract: 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: ApplicationFiled: June 16, 2021Publication date: October 7, 2021Inventors: Erik T. Nygaard, Peter L. Angelo, Scott B. Aase
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Patent number: 11043309Abstract: 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: GrantFiled: August 17, 2017Date of Patent: June 22, 2021Assignee: BWXT Technical Services Group, Inc.Inventors: Erik T. Nygaard, Peter L. Angelo, Scott B. Aase
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Patent number: 9875818Abstract: 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: GrantFiled: October 11, 2012Date of Patent: January 23, 2018Assignee: BWX Technologies, Inc.Inventors: Erik T Nygaard, Peter L Angelo, Scott B Aase
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Publication number: 20170372804Abstract: 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: ApplicationFiled: August 17, 2017Publication date: December 28, 2017Inventors: Erik T. Nygaard, Peter L. Angelo, Scott B. Aase
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Patent number: 9475706Abstract: 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: GrantFiled: October 24, 2012Date of Patent: October 25, 2016Assignee: BWXT Technical Services Group, Inc.Inventors: Timothy A Policke, Scott B Aase, William R Stagg
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Publication number: 20140112428Abstract: 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: ApplicationFiled: October 24, 2012Publication date: April 24, 2014Applicant: BABCOCK & WILCOX TECHNICAL SERVICES GROUP, INC.Inventors: Timothy A. Policke, Erik T. Nygaard, Scott B. Aase
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Publication number: 20140112858Abstract: 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: ApplicationFiled: October 24, 2012Publication date: April 24, 2014Applicant: BABCOCK & WILCOX TECHNICAL SERVICES GROUP, INC.Inventors: Timothy A. Policke, Scott B. Aase, William R. Stagg
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Publication number: 20140105349Abstract: 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: ApplicationFiled: October 11, 2012Publication date: April 17, 2014Applicant: BABCOCK & WILCOX TECHNICAL SERVICES GROUP, INC.Inventors: Erik T. Nygaard, Peter L. Angelo, Scott B. Aase
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Patent number: 8449850Abstract: 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: GrantFiled: February 17, 2011Date of Patent: May 28, 2013Assignee: Babcock & Wilcox Technical Services Group, Inc.Inventors: Daniel E. Glenn, Scott B. Aase, William R. Stagg
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Publication number: 20110206579Abstract: 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: ApplicationFiled: February 17, 2011Publication date: August 25, 2011Inventors: DANIEL E. GLENN, SCOTT B. AASE, WILLIAM R. STAGG