| AREVA NP GMBH Patent applications |
| Patent application number | Title | Published |
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| 20120121057 | NUCLEAR ENGINEERING PLANT AND CLOSURE APPARATUS FOR ITS CONTAINMENT - A nuclear engineering plant has a containment, whose interior chamber is subdivided by a wall into a systems chamber and an operating chamber which is accessible during normal operation. The containment ensures a particularly high operational reliability, in particular also in incident situations, in which hydrogen is released in the systems chamber. For this purpose, a number of overflow openings are provided in the partition wall, the respective overflow opening is closed by a closure element of a closure apparatus which opens automatically when a trigger condition associated with the respective overflow opening is reached. Closure apparatuses are provided which open both as a function of pressure and independently of pressure. The closure apparatus furthermore has a closure element containing a bursting film or a bursting diaphragm. The closure apparatus is configured such that it frees the overflow opening automatically when a predetermined environment-side trigger temperature is reached. | 05-17-2012 |
| 20120090392 | SEALING DEVICE FOR A DEVICE FOR MEASURING THE FILL LEVEL IN A FLUID CONTAINER - A sealing device for a device for measuring a fill level in a fluid container, particularly in a pressure container of a nuclear facility, includes at least one thermocouple which is connected by a pressure pipe to the pressure container and a pipeline connected to the pressure pipe to an evaluation unit. The pressure pipe and the pipeline are connected to each other by a pipe screw connection including a central part having two threaded pieces. One threaded piece is connected by a screw connection to a pipe sleeve and the other threaded piece is connected by a further screw connection to the pressure pipe. | 04-19-2012 |
| 20120023944 | DEVICE FOR PHASE SEPARATION OF A MULTIPHASE FLUID FLOW, STEAM TURBINE PLANT HAVING SUCH A DEVICE, AND ASSOCIATED OPERATING METHOD - A device for phase separating a multi-phase fluid flow has a housing configured substantially rotationally symmetrically about a center axis and encloses a hollow space, at least one in-feed line for the fluid flow configured for inflow of the fluid flow directed substantially tangentially to an interior of the housing, and at least one outlet line for the separated gaseous portion of the fluid flow. The device heats the gaseous portion of the fluid flow, such as steam, and requires little material and space. To this end, heating elements configured for heating the gaseous portion are disposed in the hollow space in an annular chamber placed concentrically about the center axis. | 02-02-2012 |
| 20110305311 | FUEL ELEMENT FOR A PRESSURIZED-WATER NUCLEAR REACTOR - In a fuel element for a pressurized-water reactor, in addition to spacers, flow-guiding structural parts are arranged. The flow guiding parts include four outer webs which, in a plane oriented perpendicularly to the central longitudinal axis, surround a square inner region of which the center point lies on the central longitudinal axis. At their lower longitudinal side facing the flowing cooling water in the operating state, the outer webs are provided with deflection lugs pointing towards the inner region and are structurally identical, wherein mutually opposite outer webs are arranged mirror-symmetrically with respect to a center plane extending in the axial direction. Such a structural part forms, at most for a number of fuel rods which is smaller than their total number in the fuel element, cells through which a respective fuel rod is guided. The number of these cells, which are situated in a row or column, is smaller than the number of the fuel rods respectively situated in this row or column. | 12-15-2011 |
| 20110303238 | PROCESS FOR DECONTAMINATING RADIOACTIVELY CONTAMINATED SURFACES - A process is provided for chemically decontaminating the surface of a metallic component. In a first treatment step, an oxide layer formed on the component by corrosion of the material of the component is detached from the surface of the component with a first aqueous treatment solution containing an organic decontamination acid. In a subsequent second treatment step, the surface which is at least partially freed of the oxide layer is treated with an aqueous solution containing an active component for removing particles which adhere to the surface. The active component is formed of at least one anionic surfactant from the group including sulphonic acids, phosphonic acids, carboxylic acids and salts of those acids. | 12-15-2011 |
| 20110227333 | END PIECE FOR A CORRUGATED HOSE AND PARTS SET CONTAINING SUCH AN END PIECE - An end piece for a corrugated hose contains a bushing having a front region and a rear region opposite of a longitudinal direction. The rear region is located inside the hose in a mounted state of the bushing. The front region has a collar forming a groove for receiving the free end of the hose. The rear region has a plurality of flexible tongues, which have a relief direction that is oriented perpendicular to the longitudinal direction of the bushing and directed toward the outer chamber of the bushing. A portion of the flexible tongues contains a radially projecting detent protrusion for implementing an engagement active in the longitudinal direction of the bushing. A retaining sleeve, received by the bushing with precise fit and, in the mounted state of the end piece, extends in an inner chamber enclosed by the bushing, limits the radial play of the flexible tongue. | 09-22-2011 |
| 20110088465 | METHOD AND DEVICE FOR MONITORING THE FILL LEVEL OF A LIQUID IN A LIQUID CONTAINER - A method for monitoring the fill level of a liquid in a liquid container, in particular for monitoring the coolant fill level in a reactor pressure vessel of a pressurized water reactor system, wherein a determination is made about the drop in the liquid level below the installed height of a heated thermal element by way of the temperature difference measured between said heated thermal element and an unheated thermal element associated therewith, both of said elements being disposed in the liquid container, said method comprising the especially reliable triggering of an alarm with a short response time while maintaining a low level of physical and controls engineering complexity when the liquid level to be monitored falls below a critical value. To this end, according to the invention the temporal progression of the temperature difference is continuously monitored for any significant increase, in particular sudden increase, within a time interval of pre-determined duration prior to the respective evaluation time, wherein an alarm signal is issued as soon as the change in the temperature difference within said time interval reaches or exceeds a pre-determined limit value. | 04-21-2011 |
| 20110013012 | METHOD AND APPARATUS FOR DETERMINING THE DEFORMATION OF A FUEL ASSEMBLY OF A PRESSURIZED WATER REACTOR - 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. Subsequently, for at least one selected reference element of the structural element, the spatial position of which is known from the deformation of the fuel assembly, at least one image coordinate is automatically ascertained and assigned to an object coordinate using a previously known imaging scale. | 01-20-2011 |
| 20100313913 | METHOD FOR CLEANING A HEAT EXCHANGER - 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. | 12-16-2010 |
| 20100296619 | Safety System for a Nuclear Plant and Nuclear Plant with a Safety System - A safety system for a nuclear plant includes a plurality of catalytic recombiner elements each triggering a recombination reaction with oxygen when hydrogen is entrained in an onflowing gas flow, so that reliable elimination of the hydrogen from the gas mixture is ensured with an especially high degree of operational safety even based on comparatively extreme conditions or scenarios of the aforementioned type. The recombiner elements and/or the flow paths each connecting two recombiner elements on the gas side are configured in such a way that a pressure pulse triggered in the gas medium by an ignition during the recombination reaction in a first recombiner element triggers a gas displacement process having a flow rate of at least 5 m/s in the onflow region of a second, adjacent recombiner element. A nuclear plant with a safety system is also provided. | 11-25-2010 |
| 20100288707 | METHOD FOR CONDITIONING A WASTE SOLUTION CONTAINING ORGANIC SUBSTANCES AND METALS IN IONIC FORM, OBTAINED DURING WET-CHEMICAL CLEANING OF CONVENTIONAL OR NUCLEAR PLANTS - A method is provided for conditioning a waste solution obtained during the wet-chemical cleaning of conventional or nuclear plants and containing organic substances and metals in ionic form. At least a portion of the organic substance is degraded by electrochemical treatment or UV radiation of the waste solution, at least one metal precipitates by the addition of phosphoric acid and a resultant phosphate precipitate is removed from the waste solution. | 11-18-2010 |
| 20100252449 | Method for Conditioning a Cleaning Solution Resulting from the Wet Chemical Cleaning of a Nuclear Steam Generator - A method for conditioning a cleaning solution resulting from the wet chemical cleaning of a nuclear steam generator, includes electrolytically treating the cleaning solution and depositing radioactive metal nuclides contained in the cleaning solution on a cathode. | 10-07-2010 |
| 20100192368 | Apparatus for Repairing a Damaged Area in an Underwater Wall Region of a Vessel or Pool - A device is provided for repairing a damaged location in an underwater region of a wall of a vessel or pool, in particular in the region of a wall of a pool of a nuclear reactor plant. The device includes a guiding system, which can be attached along a side wall at a distance therefrom and can be fixed thereto, for guiding a carriage which can be made to move in a longitudinal direction of the guiding system. Arranged on the carriage is a displaceably mounted holder for a repair support, which can be placed with an adhesive surface against the wall region containing the damaged location. With such a device, wall regions that are at a great depth and can only be accessed through narrow gaps can be repaired quickly and reliably. | 08-05-2010 |
| 20100126250 | METHOD AND APPARATUS FOR DETECTING A LEAK IN A DOUBLE PIPE - In a method for detecting a leak in a double pipe, a medium located in an intermediate chamber between the interior and exterior pipe is moved toward a first end of the pipe, whereupon the medium flows in from the second end. On the first end the medium is examined for any leakage of a characteristic material, upon the detection of which a leakage signal is generated and a location of the leakage is calculated based on the transport time of the characteristic material from the leakage to the first end and on the mass flow of the medium. A corresponding device contains a conveyor unit for moving the medium through the intermediate chamber. A material sensor is disposed at the first end for examining the medium for the characteristic material. A control and analysis unit is provided for generating a leakage signal and calculating the location of the leakage. | 05-27-2010 |
| 20100116288 | METHOD FOR DECONTAMINATING SURFACES OF NUCLEAR PLANTS WHICH HAVE BEEN CONTAMINATED WITH ALPHA EMITTERS - 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. | 05-13-2010 |
| 20100046692 | INJECTION SYSTEM AND ASSOCIATED OPERATING METHOD - 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. | 02-25-2010 |
| 20100046691 | METHOD FOR DISMANTLING A CONTROL ELEMENT OF A BOILING WATER REACTOR - A method enables dismantling of a control element of a boiling water reactor. Two control element leaves that are disposed opposite one another are separated by means of a roll-cutting method from the other two control element leaves, respectively along an intersection line extending in the longitudinal direction thereof and in the vicinity of the longitudinal center axis. | 02-25-2010 |
| 20100012154 | METHOD FOR REMOVING DEPOSITS CONTAINING MAGNETITE AND COPPER FROM CONTAINERS IN INDUSTRIAL AND POWER PLANTS - A method to remove deposits containing magnetite and copper from a container, particularly from a steam generator of a nuclear power plant. In a first step, the container is treated using an alkaline cleaning solution containing a complexing agent forming a soluble complex with iron ions, a reducing agent, and an alkalizing agent. In a second step a further complexing agent forming a more stable complex with iron III ions than the complexing agent used in the first step and an oxidant are added to the cleaning solution of the first step present in the container. | 01-21-2010 |
| 20090308144 | METHOD AND DEVICE FOR PRETREATING A FUEL ROD CLADDING TUBE FOR MATERIAL TESTS, TEST BODY AND METHOD FOR TESTING CORROSION CHARACTERISTICS - A method for treating or preparing a fuel rod cladding tube in such a way that an influence of iron oxide deposits on its surface can be studied and assessed precisely under virtually operational conditions with as little risk as possible, includes at least partially coating the fuel rod cladding tube with an iron oxide layer by immersing it in an aqueous electrolyte medium which contains iron oxide particles. The iron oxide particles are produced by anodic oxidation of an iron-containing working electrode. A test body and a device for pretreating a fuel rod cladding tube with an electrochemical three-electrode configuration, are also provided. | 12-17-2009 |
| 20090293608 | Apparatus for Measuring a Filling Level - An apparatus for measuring the filling level in a liquid vessel, in particular in a reactor vessel of a nuclear-engineering plant, with a plurality of elongate, spaced-apart measurement tubes. Each measurement tube has a number of thermocouples which are distributed in the longitudinal direction. A thermocouple, which acts as a primary signal transmitter, is heated by a heating element and is arranged on a first measurement tube, has assigned to it on the signal side an unheated thermocouple, which acts as a reference signal transmitter and is arranged on a measurement tube which is different from the first measurement tube. | 12-03-2009 |
| 20090293591 | COLLECTING LINE FOR MONITORING AND LOCATING LEAKAGES AND DEVICE HAVING THE COLLECTING LINE - A collecting line for leakage monitoring in an installation is permeable to a substance to be monitored in at least one subarea extending along the longitudinal direction. The collecting line is formed of at least two subsections that are spaced from a first end of the collecting line. The distance between the second subsection and the first end is larger than the distance between the first subsection and the first end. The permeability to the substance to be monitored is higher in the first subsection than in the second subsection. A device having the collecting line is also provided. | 12-03-2009 |
| 20090290676 | NUCLEAR-ENGINEERING PLANT AND METHOD OF OPERATING A NUCLEAR-ENGINEERING PLANT - A nuclear-engineering installation has a pressurized-water reactor and a degasification system for reactor coolant. The degasification system has a degasification column which is coupled to the primary cooling circuit of the pressurized water reactor and further includes a coolant evaporator with a first heat exchanger and a stripping vapor condenser with a second heat exchanger, wherein a partial flow of the reactor coolant flows through the heat exchanger of the coolant evaporator on the secondary side, and wherein the heat exchanger of the stripping vapor condenser is connected, on the primary side, in a vapor and gas outlet line which is connected to the degasifier column. The degasification system is intended to be configured such that, with as simple a design as possible and taking into consideration relevant safety procedures, a particularly effective and at the same time energy-efficient separation of gasses, which are dissolved in the reactor coolant and cannot be condensed, is made possible, wherein the thermal load of the assigned nuclear intermediate cooling system is furthermore intended to be kept as low as possible. To this end it is provided that the heat exchanger of the coolant evaporator is switched in a heat-pump circuit on the primary side, which heat-pump circuit is coupled to the heat exchanger of the stripping vapor condenser with respect to the heat flux, which is established during plant operation, such that the heat liberated in the strip steam condensation is transferred at least partially to the reactor coolant, which flows through the coolant evaporator, and thus causes its evaporation. | 11-26-2009 |
| 20090285346 | APPARATUS FOR ASSISTING THE LOADING OR UNLOADING OF A CORE IN A PRESSURIZED-WATER REACTOR - An apparatus for loading and unloading a core of a pressurized water reactor exerts a force acting transversely to an axial direction of a fuel assembly against an upper region of a fuel assembly adjacent a fuel assembly unloading or loading position of the core. The apparatus is an immersion vehicle being freely maneuverable under water and on which an extendable carrier arm is disposed and at least indirectly positioned against the fuel assembly. | 11-19-2009 |
| 20090252279 | Fuel Pellet for a Nuclear Reactor and Method for Producing Fuel Pellet - A fuel pellet for a nuclear reactor contains a matrix made of an oxidic nuclear fuel and a metallic phase that is deposited within or between the fuel grains and is preferably aligned in a radial direction relative to the coating surface of the pellet. A method for producing the fuel pellet includes forming slugs containing a precursor of the metallic phase, which has a melting point lying below the sintering temperature and can be transformed into the metallic phase in sintering conditions, in addition to the oxidic nuclear fuel and other optional additives. The slugs are then sintered. The slugs are heated up so quickly that at least one portion of the precursor is liquefied before being completely transformed into the metallic phase. | 10-08-2009 |
| 20090250083 | Method for the Decontamination of an Oxide Layer-containing Surface of a Component or a System of a Nuclear Facility - A method of decontaminating an oxide layer-comprising surface of a component or a system of a nuclear facility. An acidic water film is produced on the surface, the film of water is brought into contact with a gaseous acid anhydride, and the oxide layer is treated with gaseous ozone as oxidizing agent. | 10-08-2009 |
| 20090235723 | SENSOR LINE FOR MONITORING FOR AND LOCATING LEAKS AND METHOD FOR ITS PRODUCTION - A sensor line for monitoring for and locating leaks in an installation, in which chlorine escapes to the area surrounding the installation if there is a leak. The sensor line contains a carrier pipe. The wall of the carrier pipe has openings which are closed by at least one layer which is permeable for chlorine and contains a halogen-containing siloxane rubber. | 09-24-2009 |
| 20090217504 | Method for the Production of a Collecting Line for Detecting and Locating an Agent Discharging into the Environment of the Collecting Line in Case of Leakage - A method for producing a collecting line, and a collecting line produced according to the method is provided for detecting and locating an agent discharging into the environment of the collecting line in case of leakage. Such a collecting line has a carrier pipe, the wall of which is equipped with openings that are sealed by an elastic material that is permeable for the agent. Accordingly, a hose made of the permeable elastic material, the inside diameter of which is smaller than the outside diameter of the carrier pipe, is elastically expanded by creating a pressure difference between the interior and the exterior of the hose. The carrier pipe is inserted into the radially expanded hose, and the radially expanded hose is attached to the outside surface of the carrier pipe by reducing the pressure difference. | 09-03-2009 |
| 20090122945 | Fuel Assembly for a Pressurized-Water Nuclear Reactor - A fuel assembly for a pressurized water nuclear reactor contains a multiplicity of fuel rods which are guided in a plurality of axially spaced spacers which in each case form a square grid, composed of grid webs, with a multiplicity of cells arranged in rows and columns. In each case one control rod guide tube is guided through a number of these cells. At least one spacer is configured to be mechanically stronger in a first partial region than in a second partial region. In this second partial region, the spacer is provided with at least one resisting element which protrudes into a flow sub-channel formed between the fuel rods and increases the flow resistance. The resisting element counteracts a reduction associated with the mechanically weaker configuration, in the flow resistance in the second partial region and in this manner effects a homogenization of the hydraulic behavior of a spacer which is mechanically inhomogeneous on account of the varying mechanical configuration. | 05-14-2009 |
| 20090092218 | Steam Dryer for Reactor Pressure Vessel - A steam dryer through which steam flows vertically, in particular for a nuclear reactor, contains a plurality of water tanks for removing water which has been separated from the steam. The water tanks are disposed below dryer elements through which the steam flows. The water tanks of the steam dryer have in each case in the flow direction a cross section which is favorable in terms of flow. | 04-09-2009 |
| 20090067565 | Nuclear engineering plant and closure apparatus for its containment - A nuclear engineering plant has a containment, whose interior chamber is subdivided by a wall into a systems chamber and an operating chamber which is accessible during normal operation. The containment ensures a particularly high operational reliability, in particular also in incident situations, in which hydrogen is released in the systems chamber. For this purpose, a number of overflow openings are provided in the partition wall, the respective overflow opening is closed by a closure element of a closure apparatus which opens automatically when a trigger condition associated with the respective overflow opening is reached. Closure apparatuses are provided which open both as a function of pressure and independently of pressure. The closure apparatus furthermore has a closure element containing a bursting film or a bursting diaphragm. The closure apparatus is configured such that it frees the overflow opening automatically when a predetermined environment-side trigger temperature is reached. | 03-12-2009 |
| 20090048791 | Method and Device for Detecting a Pulse-Type Mechanical Effect on a System Part - A method and a device for detecting a pulse-type mechanical effect at a system component, include continuously recording an operating noise in the system component with a sensor disposed at the system component and converting the operating noise with the sensor into a measured signal subjected to a mathematical transformation. A sliding mean is calculated by determining quantiles from determined transformations and an evaluation function, which displays an application of the pulse-type mechanical effect on the system component, is derived from the sliding mean. | 02-19-2009 |
| 20080288187 | Method and Device for Detecting the Location of a Pulse-Type Mechanical Effect on a System Part - A method and device detect a position of a pulsed mechanical effect on a plant component. An operating noise in the plant component is continuously recorded by sensors which are arranged on the plant component and converted by the above into a measured signal. The measured signals of the sensors undergo a transformation in a first time window. A first evaluation function is derived from a plurality of first transformations determined in this manner, the evaluation functions display an appearance of the pulsed mechanical effect. Accordingly, when detecting an effect following the second shorter time window having the same algorithms, second transformed and respectively, second evaluation functions are derived, from which, respectively, one time point is determined. Wherein the sound signal produced by the effect impacts upon the sensor. From there, running time differences produced between the sensors can be exactly reconstructed on the position of the effect. | 11-20-2008 |
| 20080285701 | Injection System and Associated Operating Method - 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. | 11-20-2008 |
| 20080219398 | Fuel Element For A Pressurized Water Reactor - A fuel element for a nuclear reactor has a fuel rod bundle, at least one spacer with cells defined by at least one web section made from a first material and several guide tubes each running through a cell and axially fixed thereto made from a second material. The first and second materials have differing thermal expansion coefficients. The connection between the guide tube and the spacer is embodied as follows: first and second projections are directly or indirectly fixed to the guide tube. The first projections are disposed in a first axial position and the second projections are arranged at a second axial position and the projections each engage in an opening through the web section to give an axially-acting undercut. | 09-11-2008 |
