AREVA INC Patent applications |
Patent application number | Title | Published |
20150340107 | Boiling Water Reactor Core Shroud Head Bolt Retainer Tool - The inventive tool is designed to ensure proper plant operation position of the core shroud head bolt assemblies of a boiling water nuclear reactor. The tool exerts an upward pulling force on stuck retainers to return them to the locking position around the nut. The tool includes a frame, an engagement member, and a collar. The engagement member is lowered toward and end of the bolt until it comes into contact therewith. Further movement of the engagement member causes the frame and collar to move upward, lifting the retainer and extending the spring. | 11-26-2015 |
20150298266 | Two-Piece Replacement Nozzle - This invention provides an improved replacement nozzle configuration. The nozzle is provided in two pieces. A first nozzle piece is a relatively thin-walled cylinder that is inserted into the counterbored opening of a pressure vessel after the protruding portion of the original nozzle has been removed. A weld pad is attached to the pressure vessel, to which the first replacement nozzle piece is welded. Due to the reduced dimensions of the thin-walled first nozzle portion, a much smaller weld pad and pad-to-nozzle weld can be used. A second nozzle piece is positioned within the first nozzle piece and welded thereto. The existing instrumentation piping is connected to the free end of the second nozzle piece. This two-piece replacement nozzle can be implemented in approximately half the time required for the one-piece design. | 10-22-2015 |
20150243390 | SYSTEM FOR STORAGE AND TRANSPORTATION OF SPENT NUCLEAR FUEL - A concrete storage module ( | 08-27-2015 |
20140376680 | Containment Sump Ceramic Drain Plug - The present invention provides a drain plug assembly that prevents significant quantities of corium from entering the drain line. By protecting the drain line, essentially no high-activity fission products would be released to the reactor building or the environment during a severe accident. The ceramic drain plug assembly includes a drain plug base and a drain plug supported by a steel pedestal. The lower surface of the plug has a spherical shape such that the plug can be positioned within the base to block access to the drain opening provided in a central portion of the base. During normal operation conditions, the plug is retained above the base by the pedestal. During a severe accident, when corium comes into contact with the pedestal, it will melt rapidly and the drain plug will drop by gravity, effectively closing the sump drain opening and preventing the flow of corium into the drain line. | 12-25-2014 |
20140257718 | EDDY CURRENT METHOD FOR THE CHARACTERIZATION OF BROACHED TUBE SUPPORT PLATE BLOCKAGE - 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. | 09-11-2014 |
20140004220 | Press with Improved Maintenance | 01-02-2014 |
20120152059 | METHOD FOR SELECTIVELY RECOVERING AMERICIUM FROM A NITRIC AQUEOUS PHASE - A method with which americium may be selectively recovered from a nitric aqueous phase containing americium, curium and fission products including lanthanides and yttrium, but which is free of uranium, plutonium and neptunium or which only contains these three last elements in trace amounts. The method is applicable for treatment and recycling of irradiated nuclear fuels, in particular for removing americium from raffinates stemming from methods for extracting and purifying uranium and plutonium such as the PUREX and COEX™ methods. | 06-21-2012 |
20110273555 | INSPECTION VIDEO RADIATION FILTER - A method for filtering radiation on a CCD based camera inspection video, the method including: capturing video signals via the camera; converting the video signals to a plurality of digital video frames; identifying radiation bright spots, defined as xnoids, in a pixel of at least one of the frames, replacing the xnoids and surrounding pixels with corresponding pixels of another of the frames to create a filtered frame. A system for the inspection of a nuclear power plant comprising: a camera; and a computer, the computer configured to execute identifying xnoids in a pixel of at least one digitized video frame and replacing the xnoids and surrounding pixels with corresponding pixels of another of the frames to create a filtered frame. | 11-10-2011 |
20100044892 | Separating Device For Sintering Shoes - Device comprising means of separating at least two sintering shoes for transporting nuclear fuel pellets capable of moving according to a first axis (X) and of which two end faces are in contact with one another, wherein said separating means are capable of moving at least one of the two sintering shoes close to said end faces in contact, according to a second vertical axis (Y) substantially orthogonal to the first axis (X). | 02-25-2010 |