Abstract: A computer implemented method for modelizing a nuclear reactor core, including the steps of: partitioning the core in cubes to constitute nodes of a grid for computer implemented calculation, calculating neutron flux by using an iterative solving procedure of at least one eigensystem, the components of an iterant of the eigensystem corresponding either to a neutron flux, to a neutron outcurrent or to a neutron incurrent, for a respective cube to be calculated. A control parameter is varied to impact a neutron eigenvalue ? through a perturbed interface current equation and drive the neutron eigenvalue ? towards 1.
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 paramaterised 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 container for the storage of radioactive waste comprising a reversible lid having, on one hand, a first opening sealing portion provided with a first delimiting surface of an inner space wherefrom second gripping means project, said first portion being designed so as to be able to be force-fitted in an end part of a container body, and, on the other, a second sealing portion, provided with a second delimiting surface wherefrom first gripping means project, said second portion being designed so as to be able to be fitted in the end part.
Abstract: The method comprises the steps of: partitioning the core in cubes to constitute nodes of a grid for computer implemented calculation, splitting the cubes into a first category and a second category, each cube of the first category being adjacent only to cubes from the second category so that the first category and second category of cubes constitute a checkerboard-like pattern, ordering the cubes of the first category and then the cubes of the second category, calculating neutron flux and/or thermohydraulics parameters by using an iterative solving procedure of at least one linear system and/or an eigensystem, the components of an iterant of the linear system and/or the eigensystem constituting the neutron flux and/or thermohydraulics parameters to be calculated, wherein, during the iterative solving procedure, calculations are conducted on the cubes of the first category then on the cubes of the second category.
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:
Application
Filed:
August 26, 2010
Publication date:
February 3, 2011
Applicant:
AREVA NP GMBH
Inventors:
Sacha Kaercher, Wolfgang Vogt, Stefan Pfleger, Wilfried Harfst
Abstract: A control device for controlling electrical switchgear such as a circuit breaker or the like includes an actuating arm having a connection point suitable for being moved along a closed line including points P1, P2 and P3. The connection point thus moves during an opening stage for opening the moving contact, under the effect of a mechanical spring from point P1 to point P2. It also moves during a re-cocking stage for re-cocking the mechanical spring under the effect of a motor being switched on, and while keeping the moving contact in the open position, from point P2 to point P3. It also moves during a closure stage for closing the moving contact, also under the effect of the motor being switched on, from point P3 to P1. In this manner it is possible to successively perform three distinct stages of putting the actuating arm in motion, between the instant at which the moving contact leaves its closed position and the instant at which it returns thereto after having occupied its open position.
Type:
Grant
Filed:
December 19, 2006
Date of Patent:
February 1, 2011
Assignee:
Tour Areva
Inventors:
Wolfgang Grieshaber, Jean-Pierre Dupraz, Olivier Grejon, Alain Fanget, Xavier Allaire, Michel Collet
Abstract: 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:
Application
Filed:
July 22, 2010
Publication date:
January 27, 2011
Applicant:
AREVA NP Inc.
Inventors:
Mihai G. M. Pop, Anthony A. Pugh, Laurence S. Lamanna, John T. Willse
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:
Application
Filed:
February 8, 2010
Publication date:
January 27, 2011
Applicant:
AREVA NP INC
Inventors:
John C. Griffith, Joseph R. Wyatt, Mihai G.M. Pop, Jeffrey M. Fleck
Abstract: The object of the present invention is mainly a powder dispenser including a casing capable of impulsing the powder in a reciprocal movement on a plane along a determined displacement direction (X), and means (19,23) for grouping the powder along distinct axes, substantially parallel to the X direction. The object of the present invention is also a method for making pellets, notably nuclear fuel pellets, applying a dispenser according to the present invention.
Abstract: In a method for ascertaining the deformation of a fuel assembly in a pressurized-water reactor, the fuel assembly is placed in a measurement station located inside a flooded pool. The measurement station has a holding apparatus for accommodating and fixing the fuel assembly and also a camera which can be moved at least approximately parallel to its bearing axis. Digital images of the fuel assembly are recorded and stored using the camera in various axial positions, in which in each case one selected structural element of the fuel assembly is located, with the position of the fuel assembly in the recorded image depending on the deformation of the fuel assembly. Each recorded image is segmented using methods of digital image processing, and the selected structural element is identified by comparison with a virtual image of the structural element.
Abstract: A feeding system for an absorber liquid containing a neutron poison, in particular for a quick shut-down of a nuclear reactor, has a storage container for the absorber liquid and is configured for high operational reliability with simple construction. In particular, a chemical decomposition of the absorber liquid or corrosion of the container wall of the storage container is to be excluded. For this purpose, the storage container is connected to a pressure container via an overflow line, wherein the pressure container is filled with a motive fluid.
Abstract: A control apparatus for controlling electrical switchgear, the control apparatus being designed such that it is capable of performing the following in succession: during an opening stage for opening the moving contact, causing the connection end for connection to the moving contact and provided on an output member to go from the point P1 to the point P2, under the effect of an opening mechanical spring moving a moving abutment element that drives the output member by abutment; during a re-cocking stage for re-cocking the spring, moving the moving abutment element under the effect of switching on a motor, while keeping the connection end at the point P2; and during a closure stage for closing the moving contact, causing the connection end to go from the point P2 to the point P1, also under the effect of switching on the motor.
Type:
Application
Filed:
October 16, 2007
Publication date:
January 13, 2011
Applicant:
AREVA T&D SA
Inventors:
Jean-Pierre Dupraz, Michel Collet, Olivier Grejon, Xavier Allaire, Georges Doummar, Philippe Manin
Abstract: A vacuum circuit-breaker wherein one contact body is made with two windings implanted concentric with one another and connected electrically in parallel. The second winding is in the form of an solid part with an annular ring. The circuit-breaker increases the axial magnetic field (AMF) and distributes it uniformly over the contact surface so that arc extinction is improved for high short-circuit currents, typically greater than 63 kA.
Abstract: A vacuum circuit-breaker wherein at least in one of the contacts at least one stud is used as a spacer, and is disposed between the mechanical connection portion and the circular plate of the contact body in such a manner as to avoid the collapse thereof during a closing operation of the vacuum circuit-breaker, and in the closed position the contacts can withstand very high compression forces, typically greater than 700 kg-force or 2 t-force.
Type:
Application
Filed:
June 2, 2010
Publication date:
January 6, 2011
Applicant:
AREVA T & D SAS
Inventors:
Martin SCHLAUG, Uwe ERNST, Said KANTAS, Xavier GODECHOT, Laetita DALMAZIO, Pierre NEWINGER
Abstract: The invention comprises a process for estimating the concentration (C) of a chemical element in the primary coolant of a nuclear reactor, the reactor comprising means for injecting a dilution solution or a concentrated solution of the said chemical element in a predetermined concentration (C*) into the primary coolant and a sensor capable of measuring a quantity (Cm) representing the concentration of the said chemical element. The process is an iterative process comprising repeatedly in each time step k: a stage of acquiring quantities (qdk) and (qck) representing the injected flows of dilution solution and concentrated solution in step k, and a quantity (Cmk) representing the concentration measured by the sensor; a stage of calculating an estimated value (Cek+1) of the concentration of the said chemical element in the primary coolant in step k+1 on the basis of representative quantities (qdk, qck, Cmk) acquired in stage k.
Abstract: A resin removal tooling system for electric generator parallel rings including: a non-rotating sheath; a shaft mounted in the non-rotating sheath; a cleaning ball attached to the shaft, the non-rotating sheath positioning the cleaning ball; a high speed motor coupled to the shaft for rotating the shaft; a variable power supply connected to the high speed motor; and a tachometer for measuring a rotational speed of the high speed motor and the cleaning ball. A process of cleaning resin out of an electrical generator parallel ring including the following steps: inserting a cleaning ball mounted on a shaft into the parallel ring; verifying a location of the cleaning ball; rotating the shaft; measuring a rotational speed of the cleaning ball with a tachometer; and removing resin with the cleaning ball.
Type:
Application
Filed:
February 8, 2010
Publication date:
December 30, 2010
Applicant:
AREVA NP INC
Inventors:
Bruce William Schafer, Joseph Anthony Crockett
Abstract: A relief valve for discharging a dielectric gas between two volumes (V1, V2) of a high-voltage or medium-voltage interrupting chamber. There is used as a closure member a flexible metal blade secured to the body, the closure member therefore being opened by deformation of the flexible blade from a closed position (FIG. 1) in which it is pressed against a closure member seat formed in the body to a fully open position in which it fits closely against a stop member secured to the valve body whilst remaining within its elastic limit, the open passage for the gas being open in this fully open position (FIG. 1A) and the return of the blade from its fully open position to its closed position being possible because of its flexibility.
Type:
Application
Filed:
June 25, 2010
Publication date:
December 30, 2010
Applicant:
AREVA T & D SAS
Inventors:
Cyril Gregoire, Roger Ledru, Wolfgang Grieshaber
Abstract: A method for providing weld inlays and onlays to primary nozzles of a nuclear reactor comprising: providing a first welding device in a first primary nozzle of the nuclear reactor; providing a second welding device in a second primary nozzle of the nuclear reactor; providing a third welding device in a third primary nozzle of the nuclear reactor; and operating the first, second and third welding devices at the same time. Other methods are also provided.
Type:
Application
Filed:
June 8, 2010
Publication date:
December 30, 2010
Applicant:
AREVA NP INC.
Inventors:
Gary R. Poling, Brian W. Ring, Ben T. Barnett, Bradley H. Graham, Thomas N. Busic
Abstract: A terminal end-piece for a fuel assembly of a pressurized water nuclear reactor, the assembly having fuel rods and a skeleton for supporting the fuel rods, the fuel rods extending in a longitudinal direction and being arranged at the nodes of a substantially regular network, the support skeleton comprising two terminal end-pieces and guide tubes that connect the terminal end-pieces, the fuel rods being arranged longitudinally between the terminal end-pieces, characterized in that the end-piece comprises noses for orientating the flow of a coolant fluid of the reactor along the adjacent longitudinal ends of the fuel rods, the noses being arranged in nodes of the substantially regular network in order to be positioned in a longitudinal continuation of at least some of the fuel rods and/or at least some of the guide tubes of the support skeleton.
Type:
Grant
Filed:
December 17, 2004
Date of Patent:
December 21, 2010
Assignee:
Areva NP
Inventors:
Eric Labarriere, Angelo Beati, Michel Bonnamour
Abstract: A physical-chemical method for cleaning a secondary chamber of a heat exchanger in a nuclear facility, includes drying the secondary chamber and introducing a cleaning solution into the secondary chamber to treat deposits present in the secondary chamber.