Patents by Inventor Mihai G. M. Pop
Mihai G. M. Pop 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: 10102930Abstract: A nuclear fuel cladding is provided. The nuclear fuel cladding includes a base cladding; and at least one nanomaterial layer deposited on a surface of the base cladding, the nanomaterial layer having an average grain size of between 5 to 400 nanometers. A method of manufacturing nuclear fuel cladding is also provided. The method includes depositing nanoparticles on a base cladding to form at least one nanomaterial layer, the nanoparticles having an average grain size of between 5 to 400 nanometers.Type: GrantFiled: November 13, 2013Date of Patent: October 16, 2018Assignee: Framatome Inc.Inventors: Mihai G. M. Pop, Laurence Lamanna, Garry Garner, Brian Lockamon
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Patent number: 10020078Abstract: A fuel rod for a nuclear fission reactor is disclosed and claimed. The fuel rod includes an elongate hollow cladding configured to retain a nuclear fuel therein. The cladding includes an elongate hollow tube. Fiber layers are positioned around the outside surface of the tube or within the tube forming an integral part thereof. Both the tube and the fibers are formed of a ceramic material. A fuel assembly including a plurality of such fuel rods is also disclosed and claimed.Type: GrantFiled: April 10, 2014Date of Patent: July 10, 2018Assignee: Framatome Inc.Inventor: Mihai G. M. Pop
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Patent number: 9721680Abstract: A method of operating a nuclear reactor is provided. The method includes defining a layer increment of a deposit layer modeling a deposit on a heat transfer surface of the nuclear reactor; periodically updating a thickness of the deposit layer by adding the layer increment to the deposit layer; recalculating properties of the deposit layer after each layer increment is added to the deposit layer; determining a temperature related variable of the heat transfer surface as a function of the recalculated properties of the deposit layer; and altering operation of the nuclear reactor when the temperature related variable of the heat transfer surface reaches a predetermined value. A method of modeling a deposit on a heat transfer surface of a nuclear reactor is also provided.Type: GrantFiled: September 30, 2013Date of Patent: August 1, 2017Assignee: AREVA Inc.Inventors: Mihai G. M. Pop, Joseph R. Wyatt, John C. Griffith
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Patent number: 9530527Abstract: A method to perform an analysis of two types of CRUD on a nuclear fuel rod, including providing a nuclear fuel rod with a first and second layer of CRUD on an exterior of the fuel rod; brushing the first layer of CRUD from the fuel rod with a CRUD tool on a selected area; wherein the tool has a brushing device, a force applied to the brushing device on the fuel rod to remove the first layer of CRUD, the force being sufficient enough to perform such removal; collecting the first layer of CRUD from the brushing device, scraping the second layer of CRUD from the fuel rod in the selected area with the tool, wherein the tool has a scraping device and a second force is applied to the tool for scraping, collecting the second layer of CRUD from the scraping device, and analyzing the first layer and second layer of CRUD separately with a scanning electron microscope.Type: GrantFiled: July 22, 2010Date of Patent: December 27, 2016Assignee: AREVA Inc.Inventors: Mihai G. M. Pop, Anthony A. Pugh, Laurence S. Lamanna, John T. Willse
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Patent number: 9478319Abstract: A method of operating a power generator is provided. The method includes determining an amount of oxides on a heat transfer surface of the power generator as a function of a concentration of a noble metal substance in the oxides; and altering operation of the power generator when the amount of oxides on the heat transfer surface reaches a predetermined value. A method of operating a nuclear reactor is also provided.Type: GrantFiled: January 28, 2013Date of Patent: October 25, 2016Assignee: AREVA Inc.Inventors: Carola A. Gregorich, John M. Riddle, Mihai G. M. Pop
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Patent number: 9472311Abstract: A method to assess light water reactor fuel integrity is presented having the steps of granting access in a nuclear reactor fuel pool to at least one of a discharged fuel rod and a nuclear fuel assembly, calculating an operating flux for the fuel rod, measuring a thickness of CRUD on the fuel rod, measuring a thickness of oxide on the fuel rod, calculating a maximized flux for the at least one fuel rod for a position of the one fuel rod in a nuclear reactor, calculating a maximized deposit for the fuel rod, calculating a maximized oxide thickness for the fuel rod, calculating a fuel condition index of the fuel rod, comparing the fuel condition index to an index constant, and removing the fuel rod from operation when the fuel condition index is greater than the index constant.Type: GrantFiled: April 23, 2014Date of Patent: October 18, 2016Assignee: AREVA Inc.Inventors: Mihai G. M. Pop, Brian Glenn Lockamon
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Publication number: 20160268010Abstract: A method to assess light water reactor fuel integrity is presented having the steps of granting access in a nuclear reactor fuel pool to at least one of a discharged fuel rod and a nuclear fuel assembly, calculating an operating flux for the fuel rod, measuring a thickness of CRUD on the fuel rod, measuring a thickness of oxide on the fuel rod, calculating a maximized flux for the at least one fuel rod for a position of the one fuel rod in a nuclear reactor, calculating a maximized deposit for the fuel rod, calculating a maximized oxide thickness for the fuel rod, calculating a fuel condition index of the fuel rod, comparing the fuel condition index to an index constant, and removing the fuel rod from operation when the fuel condition index is greater than the index constant.Type: ApplicationFiled: April 23, 2014Publication date: September 15, 2016Applicant: AREVA Inc.Inventors: Mihai G. M. Pop, Brian Glenn Lockamon
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Publication number: 20160099084Abstract: A method of injecting platinum into a Boiling Water Reactor is provided. The Boiling Water Reactor includes a reactor core including a plurality of fuel rods having a zirconium alloy cladding. The method includes injecting a first platinate compound and a second platinate compound into a nuclear reactor. The first platinate compound is non-alkalizing and the second platinate compound includes an alkalizing element. The first platinate compound and the second platinate compound are injected such that the second platinate compound injected does not exceed a predetermined threshold or such that a value related to an alkalizing element of the second platinate compound does not exceed a predetermined threshold.Type: ApplicationFiled: October 2, 2014Publication date: April 7, 2016Inventors: John M. Riddle, Mihai G. M. Pop, Larry S. Lamanna
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Publication number: 20150131768Abstract: A nuclear fuel cladding is provided. The nuclear fuel cladding includes a base cladding; and at least one nanomaterial layer deposited on a surface of the base cladding, the nanomaterial layer having an average grain size of between 5 to 400 nanometers. A method of manufacturing nuclear fuel cladding is also provided. The method includes depositing nanoparticles on a base cladding to form at least one nanomaterial layer, the nanoparticles having an average grain size of between 5 to 400 nanometers.Type: ApplicationFiled: November 13, 2013Publication date: May 14, 2015Applicant: AREVA NP INC.Inventors: Mihai G. M. Pop, Laurence Lamanna, Garry Garner, Brian Lockamon
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Publication number: 20150092901Abstract: A method of operating a nuclear reactor is provided. The method includes defining a layer increment of a deposit layer modeling a deposit on a heat transfer surface of the nuclear reactor; periodically updating a thickness of the deposit layer by adding the layer increment to the deposit layer; recalculating properties of the deposit layer after each layer increment is added to the deposit layer; determining a temperature related variable of the heat transfer surface as a function of the recalculated properties of the deposit layer; and altering operation of the nuclear reactor when the temperature related variable of the heat transfer surface reaches a predetermined value. A method of modeling a deposit on a heat transfer surface of a nuclear reactor is also provided.Type: ApplicationFiled: September 30, 2013Publication date: April 2, 2015Applicant: AREVA NP Inc.Inventors: Mihai G. M. Pop, Joseph R. Wyatt, John C. Griffith
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Patent number: 8976920Abstract: A nuclear power plant with an improved cooling system using nanoparticles in solid or fluid form is provided. The nanoparticles are delivered in locations such as the cold leg accumulator and high and low pressure pumps of an emergency core cooling system. Motor driven valves and pressurization can aid in the delivery. Methods for providing the nanoparticles are also provided.Type: GrantFiled: March 2, 2007Date of Patent: March 10, 2015Assignee: Areva NPInventors: Mihai G. M. Pop, Brian Glenn Lockamon
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Publication number: 20140307845Abstract: A fuel rod for a nuclear fission reactor is disclosed and claimed. The fuel rod includes an elongate hollow cladding configured to retain a nuclear fuel therein. The cladding includes an elongate hollow tube. Fiber layers are positioned around the outside surface of the tube or within the tube forming an integral part thereof. Both the tube and the fibers are formed of a ceramic material. A fuel assembly including a plurality of such fuel rods is also disclosed and claimed.Type: ApplicationFiled: April 10, 2014Publication date: October 16, 2014Inventor: Mihai G. M. Pop
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Publication number: 20140257718Abstract: A method for determining tube support plate blockage of a steam generator includes the following steps: measuring at least five different eddy current values per tube support intersection; calculating a nominal clean fit radius of flow hole; determining a center signal response; converting the center signal response to a deposit thickness; determine an edge reduction; converting the edge reduction to an edge thickness; calculating the resulting flow hole radius; verifying the reasonableness of the resulting flow hole radius; and determining a virtual calibration range.Type: ApplicationFiled: May 22, 2014Publication date: September 11, 2014Applicant: AREVA Inc.Inventors: John C. Griffith, Joseph R. Wyatt, Mihai G.M. Pop, Jeffrey M. Fleck
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Patent number: 8804897Abstract: A method to analyze crystals in a deposit on a surface of a nuclear generating station heating surface, wherein the method extracts a sample of material from the surface of the nuclear generating station heating surface and also includes conducting at least one of a high resolution scanning electron microscope/energy dispersive X-ray spectrometry of the sample and a scanning transmission electron microscope/selected area electron diffraction/spot and elemental mapping analysis of the sample.Type: GrantFiled: July 21, 2006Date of Patent: August 12, 2014Assignee: AREVA Inc.Inventors: Mihai G. M. Pop, Brian Glenn Lockamon, Vladimir Oleshko, James Howe
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Publication number: 20140211903Abstract: A method of operating a power generator is provided. The method includes determining an amount of oxides on a heat transfer surface of the power generator as a function of a concentration of a noble metal substance in the oxides; and altering operation of the power generator when the amount of oxides on the heat transfer surface reaches a predetermined value. A method of operating a nuclear reactor is also provided.Type: ApplicationFiled: January 28, 2013Publication date: July 31, 2014Applicant: AREVA NP INC.Inventors: Carola A. Gregorich, John M. Riddle, Mihai G. M. Pop
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Patent number: 8774341Abstract: A nuclear power plant is provided including a BWR, a reactor cooling system cooling the BWR, an HWC hydrogen injection system connected to the reactor cooling system and an alcohol injection system connected to the reactor cooling system. Methods for providing methanol and hydrogen are also provided.Type: GrantFiled: September 28, 2007Date of Patent: July 8, 2014Assignees: AREVA Inc., AREVA NP GmbHInventors: Bernhard Stellwag, Mihai G. M. Pop
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Publication number: 20140183356Abstract: A method to analyze crystals in a deposit on a surface of a nuclear generating station heating surface, wherein the method extracts a sample of material from the surface of the nuclear generating station heating surface and also includes conducting at least one of a high resolution scanning electron microscope/energy dispersive X-ray spectrometry of the sample and a scanning transmission electron microscope/selected area electron diffraction/spot and elemental mapping analysis of the sample.Type: ApplicationFiled: July 21, 2006Publication date: July 3, 2014Inventors: Mihai G.M. Pop, Brian Glenn Lockamon, Vladimir Oleshko, James Howe
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Patent number: 8744781Abstract: A method for determining tube support plate blockage of a steam generator includes the following steps: measuring at least five different eddy current values per tube support intersection; calculating a nominal clean fit radius of flow hole; determining a center signal response; converting the center signal response to a deposit thickness; determine an edge reduction; converting the edge reduction to an edge thickness; calculating the resulting flow hole radius; verifying the reasonableness of the resulting flow hole radius; and determining a virtual calibration range.Type: GrantFiled: August 20, 2013Date of Patent: June 3, 2014Assignee: AREVA Inc.Inventors: John C. Griffith, Joseph R. Wyatt, Mihai G. M. Pop, Jeffrey M. Fleck
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Patent number: 8737557Abstract: A method to assess light water reactor fuel integrity is presented having the steps of granting access in a nuclear reactor fuel pool to at least one of a discharged fuel rod and a nuclear fuel assembly, calculating an operating flux for the fuel rod, measuring a thickness of CRUD on the fuel rod, measuring a thickness of oxide on the fuel rod, calculating a maximized flux for the at least one fuel rod for a position of the one fuel rod in a nuclear reactor, calculating a maximized deposit for the fuel rod, calculating a maximized oxide thickness for the fuel rod, calculating a fuel condition index of the fuel rod, comparing the fuel condition index to an index constant, and removing the fuel rod from operation when the fuel condition index is greater than the index constant.Type: GrantFiled: July 21, 2006Date of Patent: May 27, 2014Assignee: AREVA Inc.Inventors: Mihai G. M. Pop, Brian Glenn Lockamon
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Publication number: 20130338940Abstract: A method for determining tube support plate blockage of a steam generator includes the following steps: measuring at least five different eddy current values per tube support intersection; calculating a nominal clean fit radius of flow hole; determining a center signal response; converting the center signal response to a deposit thickness; determine an edge reduction; converting the edge reduction to an edge thickness; calculating the resulting flow hole radius; verifying the reasonableness of the resulting flow hole radius; and determining a virtual calibration range.Type: ApplicationFiled: August 20, 2013Publication date: December 19, 2013Applicant: AREVA NP Inc.Inventors: John C. Griffith, Joseph R. Wyatt, Mihai G. M. Pop, Jeffrey M. Fleck