Abstract: A pencil-shaped electrical heating element, in particular for application in a device for measuring filling level in a liquid container, in particular in a reactor chamber of a nuclear plant, contains an electrically-conducting sleeve and at least one electric line embedded therein which is in conducting contact with the sleeve. The electrical line has at least two line sections with differing electrical properties and/or thermal conductivities.
Type:
Grant
Filed:
August 26, 2010
Date of Patent:
June 3, 2014
Assignee:
Areva GmbH
Inventors:
Sacha Kaercher, Wolfgang Vogt, Stefan Pfleger, Wilfried Harfst
Abstract: 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:
Grant
Filed:
August 20, 2013
Date of Patent:
June 3, 2014
Assignee:
AREVA Inc.
Inventors:
John C. Griffith, Joseph R. Wyatt, Mihai G. M. Pop, Jeffrey M. Fleck
Abstract: A plate for a fuel cell consisting of a stack of plates and membrane electrode assemblies is provided. The plate includes at least one striated sealing surface for bearing in a sealed manner against a membrane electrode assembly or against another fuel cell plate. The plate is a bipolar plate, a monopolar plate, or an elementary plate of such a bipolar or monopolar plate.
Type:
Application
Filed:
July 9, 2012
Publication date:
May 29, 2014
Applicant:
AREVA Stockage d'Energie
Inventors:
Florent Beille, Christian Quintieri, Didier Vannucci, Frédéric Le Fol
Abstract: A fuel cell separator plate is provided. The fuel cell separator plate includes at least one groove formed in a face of the separator plate so as to feed reactant gas to a membrane electrode assembly applied against the face of the separator plate, the groove comprising an inlet section and an outlet section. The fuel cell separator plate also includes injection means configured so as to inject gas into at least one intermediate section of the groove, situated between the inlet section and the outlet section.
Abstract: 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.
Abstract: A device for producing and storing dioxygen and/or dihydrogen is provided. The device includes a source of dioxygen and dihydrogen, and a high pressure tank to store the dioxygen, respectively dihydrogen, at high pressure, in fluid communication with the source. The device further includes a bypass line connecting an outlet of dioxygen, respectively of dihydrogen, of the source with an outlet of dioxygen, respectively of dihydrogen, of the production and storage device, bypassing the high pressure tank, the bypass line being fed through a pressure regulator to reduce the pressure in the bypass line; and a device for measuring the concentration of dihydrogen, respectively of dioxygen, in the dioxygen respectively in the dihydrogen produced by the source, the measuring device being arranged on the bypass line.
Abstract: A method for producing a uranium oxide catalyst body includes the following steps: UO2+x powder, with x?0.7, having a purity of at least 50% is sintered in a first sintering process to obtain a UO2+y intermediate, where y?0.25. Then the UO2+y intermediate is oxidized with oxygen and converted in the process into a U3O8?z powder, with z?1. The U3O8?z powder is pressed to form a blank having a shape that corresponds with the catalyst body to be produced. The blank is sintered in a second sintering process at a temperature of at least 900° C. in an oxygen-containing sintering atmosphere.
Abstract: A method produces a welded connection between first and second components each having inner and outer sides interconnected by an end face. The first component has a ferritic basic body carrying a plating at the inside and having an end face with a buffer layer of Ni-based alloy. The second component is of austenitic material. The end faces of the components enclose a weld groove. An austenitic root, connecting the plating to the end face of the second component, is welded in the weld groove. An intermediate layer of a nickel alloy having at least 90% nickel is welded onto the root. The intermediate layer is connected to the end faces of the plating and the second component. A weld seam is then produced in the remaining weld groove using a nickel-based welding additive. A method for repairing a welded connection between first and second components is also provided.
Type:
Grant
Filed:
June 4, 2012
Date of Patent:
May 20, 2014
Assignee:
Areva GmbH
Inventors:
Erhard Brueckner, Gerhard Engelhard, Siegried Guegel
Abstract: A method for regenerating a solid filter containing iodine in the form of silver iodide and/or iodate and possibly molecular iodine physisorbed, in a solid filter containing silver in the form of nitrate. The iodine is extracted from the filter by putting the filter into contact with a basic aqueous solution containing a reducing agent. The extraction is achieved at room temperature, and then the filter is separated from this basic aqueous solution. Next, silver is extracted from the filter by putting the filter into contact with an acid aqueous solution. The filter is then separated from the acid aqueous solution. Finally, the filter is impregnated with silver by putting the filter into contact with a silver nitrate solution and then drying the filter. This method can be used in nuclear installations, notably factories for reprocessing used nuclear fuels.
Type:
Grant
Filed:
July 16, 2010
Date of Patent:
May 6, 2014
Assignees:
Areva NC, Commissariat a l'Energie Atomique et aux Energies Alternatives
Abstract: A method for installing industrial components in an environment is provided, in which, with the aid of a computer-assisted design model representing the theoretical layout of the industrial components in the environment, various measuring points of the theoretical positioning of the supports of each component are determined, those theoretical measuring points are codified with values, parameterisable model measuring ranges are parameterized by the codified values, and at least one measuring device is controlled with the aid of the codified values by application of the corresponding range in order to compare the actual positioning points in the environment as a function of theoretical positioning points of the supports of each component. The method is applicable to the installation of the components of the loops of the primary circuits of nuclear power stations.
Abstract: A nuclear fuel assembly bottom nozzle, of the type including a perforated plate to allow water to pass through it, the nozzle having lateral faces, and at least one anti-debris element positioned on a lateral face to block out debris likely to infiltrate between the bottom nozzle and another adjacent bottom nozzle, characterized in that, in the free state, the or each anti-debris element permanently projects from the lateral face on which it is positioned, the or each anti-debris element being elastically deformable so as to retract towards the lateral face in the event of a force being exerted on the anti-debris element towards the lateral face.
Abstract: A machine comprising two rollers for ovalizing a nuclear fuel cladding to crush the content thereof allowing its easy release even if the pellets are arranged in the cladding with little clearance. The opposite inclinations of the rollers promote automatic forward travel of the claddings. The opening and the inclination of the claddings lead to release of the crushed fuel. The rollers are biconical, with an input portion of increasing diameter and an output portion of decreasing diameter, to apply sufficient ovalizations to crush the fuel while restoring rotundity to the cladding when it leaves the machine, to facilitate the outflow of debris.
Abstract: A tool for inspecting a cell formed by grid beams of a top guide structure in a nuclear reactor is provided. The tool includes a camera; a support structure coupled to the camera for contacting at least one of the grid beams to support the camera within the cell; and at least one actuator moving the camera with respect to the support structure and along one of the grid beams, the at least one actuator coupling the camera to the support structure. A method for inspecting a cell formed by grid beams of a top guide structure in a nuclear reactor is also provided.
Abstract: A method for decontaminating nuclear plant surfaces, which have been contaminated with alpha emitters, is carried out subsequently to a decontamination process which is aimed at the removal of oxide layers. The surfaces are treated with an aqueous solution which contains a cationic or zwitterionic surfactant and oxalic acid. At least a part of the solution, after having acted on a surface, is conducted across an ion exchanger.
Type:
Grant
Filed:
May 27, 2009
Date of Patent:
April 22, 2014
Assignee:
Areva GmbH
Inventors:
Rainer Gassen, Christoph Stiepani, Horst-Otto Bertholdt, Bertram Zeiler
Abstract: The geometric dimensions and shape of a device for removing solid particles from the cooling medium that is circulated in the primary circuit of a nuclear reactor, in particular a boiling water nuclear reactor, are such that the device can be inserted in lieu of a fuel element or fuel assembly into an empty fuel element or assembly position of the reactor core of the nuclear reactor.
Type:
Grant
Filed:
January 16, 2009
Date of Patent:
April 22, 2014
Assignee:
Areva GmbH
Inventors:
Hartmut Lelickens, Reazul Huq, Werner Meier, Jochen Heinecke
Abstract: A method for cleaning and conditioning the water-steam circuit of a power plant, especially of a nuclear power plant, uses an amine as a film-forming agent. The amine is metered into the working medium circulating in the water-steam circuit. The film-forming agent forms a hydrophobic film on the surfaces of the circuit. During the process, the concentration of at least one impurity contained in the water and the concentration of the film-forming agent in at least in the feed water of the steam generator are measured and monitored. The concentration of the film-forming agent is varied, as needed, subject to the concentration of the impurity.
Abstract: A method for conditioning the circulatory system (1) of a power plant is especially suited for a nuclear power plant. An amine, which is a film-forming agent, is metered into the working medium circulating in the circulatory system. The film-forming agent forms a hydrophobic film on the surfaces of the circulatory system. During the process, the concentration of the film-forming agent is monitored in at least one measuring point by way of measurement, and metering of the film-forming agent is stopped once its concentration in the working medium has reached a value of 1 ppm to 2 ppm in at least one measuring point M1.
Abstract: A device separates a fluid mass flow in a nuclear plant. The device contains a primary end piece for conducting the fluid mass flow and a plurality of secondary end pieces for conducting a plurality of separate partial flows of the fluid mass flow. A number of separating elements is provided in the area within the primary end piece, and each of the partial areas defined by the separating element or the separating elements opens in a secondary end piece clearly assigned to the partial area.
Type:
Application
Filed:
December 6, 2013
Publication date:
April 3, 2014
Applicant:
AREVA GMBH
Inventors:
ROBERT BUETTNER, GUENTHER SCHULZE, RALF WALTERSKOETTER
Abstract: The invention relates to a method of determining at least one technological uncertainty factor in respect of nuclear fuel elements (23) as a function of variations in the production parameters of the elements (23) in relation to nominal values. The inventive method comprises a step involving the use, for at least one production parameter, of a collective variation in said parameter in relation to the nominal value within a batch of produced elements (23). The invention can be used, for example, to design, produce and check pellets for light water reactors.
Abstract: An anchoring system for forming a non-releasable connection between a concrete component, has a reinforcement containing at least one steel bar mesh, and a steel component. At least one anchoring element formed of an anchor strip is cast into the concrete component in such a way that at least one connecting surface projects at least partially from the concrete component. This improves the loadability of the anchoring. For this purpose, the anchor strip has a number of recesses which extend at least partially into the concrete component and which are each traversed by at least one steel bar of the steel bar mesh.
Type:
Application
Filed:
December 3, 2013
Publication date:
March 27, 2014
Applicant:
AREVA GMBH
Inventors:
CHRISTIAN KRUMB, SERGE NABOISHIKOV, MARCO SCHIPPERS