Areva Np Gmbh

Areva Gmbh

Framatome Gmbh

Framatome Anp Gmbh

Mihai G M Pop

Brian Lockamon

John Carroll Griffith

Laurence Lamanna

John T Willse

Joseph R Wyatt

Bernhard Stellwag

William Edward Allmon

Jeffrey M Fleck

Kent Colgan

Anthony A Pugh

John Morrison Riddle

Renate Kilian

Vladimir Oleshko

Hans-Jürgen Sell

James Howe

Carola A Gregorich

Garry Garner

Brian Glenn Lockamon

John C Griffith

Laurence S Lamanna

Brian G Lockamon

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.

Nuclear fuel rod cladding including a metal nanomaterial layer

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.

Composite fuel rod cladding

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.

Operating a nuclear reactor using a deposit model of a nuclear reactor heat transfer surface

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.

Advanced fuel CRUD sampling tool method

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.

Method of operating a power generator based on noble metal induced oxidation of a heat transfer surface

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.

Method for prediction of light water reactor fuel defects using a fuel condition index

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.

Nuclear power plant using nanoparticles in emergency systems and related method

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.

Integrated method to analyze crystals in deposits

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.

Boiling water reactor nuclear power plant with alcohol injection

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.

Eddy current method for the characterization of broached tube support plate blockage

Eddy current for the characterization of broached tube support plate blockage

The invention provides at least two electrochemical sensors positioned in a nuclear reactor or in a system adjacent to the nuclear reactor, wherein at least one of the at least two electrochemical sensors has a heated zirconium electrode, and the at least two electrochemical sensors produce voltages proportional to an electrochemical corrosion potential for a surface that each of the at least two electrochemical sensors are installed upon. The invention also provides an arrangement configured to accept the voltages produced by the at least two electrochemical sensors, wherein the arrangement is configured to determine an electrochemical corrosion potential of a zirconium fuel rod in the nuclear reactor based upon the voltages of the at least two electrochemical sensors.

Electrochemical corrosion potential device and method

A nuclear power plant with an improved cooling system using nanoparticles in solid or fluid form to improve heat transfer and reduce corrosion is provided. The nanoparticles are delivered to a closed cooling circuit such as a CCWS. Methods for providing the nanoparticles are also provided.

Growing community of inventors

Lynchburg, VA, United States of America

Mihai G M Pop