General Electric Company

Ralph J Reda

Robert A Haughton

Michael T Kiernan

Johnny R Skipper

William Earl Russell, Ii

James D Landry

Robert J Sziemkiewicz

Ronald V Ryan

Ralph K Furches

Frank W Cloudman, Jr

Joel L Pickett

A nuclear reactor core performance data visualization system provides a method and apparatus for extracting and visually displaying large amounts of numerical performance data acquired from an operational nuclear reactor or from a nuclear reactor core simulator. The visualization system apparatus includes a color display device, a digital computer having a data storage memory, and one or more data communications links for communicating with reactor core sensors and/or other computers. After acquiring performance parameter data, the visualization system computer extracts selected performance data and constructs two distinct data arrays in memory that are used in creating formatted files for generating specific types of visual displays. A first data array, containing time-varying reactor performance parameter data corresponding to the performance of reactor core elements in two dimensions over a predetermined duration of time, is used, to create digital image animation files for displaying dynamic color-coded graphics, including reactor core element diagrams and multi-ordinate graphs. Once animated, the displayed graphics allow the user to view a time-wise evolution of the changing numerical values for selected core parameters and other time-dependent variables. A second data array, containing spatially-related core performance parameter data corresponding to performance of reactor core elements in three dimensions at one or more selected point(s) in time, is used to create virtual reality modeling language (VRML) files for displaying a virtual 3-D color-coded reactor core model that can be manipulated in three dimensions by the viewer.

Nuclear reactor core performance data visualization system

A TIG welding system for controlling the weld shape for the seal welding of a small pressurization hole in the end plug of nuclear fuel rods. The controlled shape of the seal weld enables improved ultrasonic detection capabilities. The system achieves the desired weld shape by controlling the pressure differential between the interior and exterior volumes of the fuel rod. The weld box pressure is decreased in accordance with Boyle's law while the weld material for sealing the hole is molten. The system uses an output from the weld electronics as an input to a programmable logic controller ('PLC'). After a programmed time delay, the PLC outputs a signal to a solenoid valve to open a 'ballast' volume. The expansion of gas from the weld box into the ballast volume causes a sudden drop in pressure to a level below the pressure inside the fuel rod. As a result of this pressure differential, the molten weld material forms a concave weld upon solidification.

Weld shape control system for TIG welding of small pressurization hole

In an automated final weld apparatus, a transporter conveys nuclear fuel-loaded cladding tubes successively to a check station to verify the presence of a plenum spring in the open end of each cladding tube, a reader station where a unique first end plug serial number is read, an evacuation/backfill station where the cladding tube is backfilled with helium, a seam welding station where a final end plug is welded to the cladding tube open end, and a seal weld station where the tube is pressurized with helium through a pressurization hole in the final end plug, whereupon the pressurization hole is welded closed. After checking for helium leakage, the seam weld is inspected in a succession of inspection stations, and, depending on inspection results, the finished nuclear fuel rods are sorted into accepted and rejected lots.

Apparatus for assembling and welding final end plugs to nuclear

Nuclear fuel rod having concave weld across pressurization hole in end

A system for monitoring the radioactivity of a liquid waste stream includes a pair of tanks into which the liquid waste stream is directed during alternating fill cycles. At the conclusion of each fill cycle, the liquid waste is recirculated through the chamber of a radioactivity monitor. A pair of opposed radiation detectors, external to the chamber, generate activity measurements to a controller indicative of the radionuclide concentration levels in the liquid waste. The tanks are then emptied either to the environment or back to a decontamination facility for further processing depending on the indicated radionuclide concentration level. System operation, including periodic servicing of the monitor, is automatically coordinated by the controller to avoid interruption of the liquid waste stream filling the tanks.

System for monitoring the radioactivity of liquid waste

Growing community of inventors

Wilmington, NC, United States of America

Ralph J Reda