Abstract:
A contrast control device is provided. The device of the invention includes a detecting unit, a judging unit, a backlight control unit, a gain generating unit and a contrast gain processing unit. The detecting unit calculates an average value and detects a maximum value of a current image. The judging unit generates a gain index and a brightness index according to the average value. The backlight control unit generates a backlight control signal according to the brightness index. The gain generating unit generates a first contrast gain value and a soft-clamping gain value according to the gain index, the average value and the maximum value and then selects one from the first contrast gain value and the soft-clamping gain value for output as a second contrast gain value according to an input pixel value of the current image. The contrast gain processing unit generates an output pixel value according to the second contrast gain value and the input pixel value.
Abstract:
A method for creating a Gamma look-up table (LUT) includes: calculating interpolated display characteristics of a plurality of colors by using a nonlinear interpolation algorithm based on a plurality of display characteristics of the predetermined patterns wherein the number of the display characteristics is smaller than the product of the number of the colors and the number of the interpolated display characteristics of the colors; and correcting the interpolated display characteristics of the colors on the basis of a maximum display characteristic value and a reference gamma value so that the Gamma look-up table is created. The predetermined patterns comprise a plurality of gray level patterns which one-by-one correspond to a plurality of levels, and the interval of a pair of adjacent gray level patterns among the gray level patterns is different from the interval of another pair of adjacent gray level patterns among the gray level patterns.
Abstract:
A plate mounted fuel assembly hold-down system that provides a defined channel for both the insertion and removal of reactor head mounted, fixed in-core detector instrumentation, provides a guided path for the fixed in-core detector during insertion, and shields the instrument shroud against coolant cross flow. The hold-down assembly includes a base plate that seats on the adapter plate of the fuel assembly and has openings that align with the control rod guide thimbles. A hollow sleeve extends through and below a central opening in the base plate to mate with the fuel assembly instrument thimble. The sleeve extends above the base plate and through and above an upper core plate of the reactor. A hold-down bar is slidably mounted on the sleeve and is restrained below the top of the sleeve. A spring is positioned around the sleeve and is captured between the hold-down bar and the base plate.
Abstract:
An improved grid for use in a fuel assembly of a nuclear reactor includes a plurality of straps connected in a lattice, with a plurality of mixing vanes being disposed on the straps and being arranged such that the hydraulic forces on the mixing vanes generally cancel one another out. The mixing vanes of diagonal quadrants of the grid are generally aligned with diagonally disposed imaginary alignment planes. Each strap includes a plurality of strap members, with each strap member including a spring and a pair of dimples. The spring includes a contoured spring embossment having a greater radius of curvature in a relaxed condition than the radius of a fuel rod. Each dimple includes a similarly configured contoured dimple embossment. The spring embossment is mounted on a pair of legs that extend nonlinearly between a first plate and a second plate of each strap member to increase compliance thereof.
Abstract:
A color management circuit and a related color management method are provided. The color management circuit is disposed in a display device which has a panel provided with a panel conversion characteristic. The color management circuit includes: a first nonlinear conversion circuit, a color matrix conversion circuit and a second nonlinear conversion circuit. The first nonlinear conversion circuit is utilized for performing a first nonlinear conversion upon a color data to generate a first conversion data. The color matrix conversion circuit is utilized for performing a liner matrix calculation upon the first conversion data to generate a matrix calculation data. The second nonlinear conversion circuit is utilized for performing a second nonlinear conversion upon the matrix calculation data to generate a second conversion data to the panel, wherein a combined conversion characteristic of the second conversion characteristic with the panel conversion characteristic is substantially linear.
Abstract:
A nuclear fuel assembly having a plurality of multi-leaf hold down spring sets extending from a top nozzle. Each spring set consists of a multiple number of springs leafs in order to provide a large working range of spring deflection. Each spring leaf has a straight, flat base section followed by a straight, flat tapered beam with a secondary spring set having a curvature at its peripheral end.
Abstract:
A combination type of socket with power source management which includes a power source protection and filter body, a multi-hole outlet extension socket body, an automatic timing socket body, a synchronized main/secondary socket body, a main plug provided to the power source protection and filter body for connection to a common power source having a power source switch and a socket for connection with extension outlet socket. The socket is characterized in that the power source protection and filter body is provided with a power source quality processing circuit, excess voltage input prevention circuit, low high current indication alarm circuit, low high voltage indication alarm circuit, control circuit for voltage, and current indicator such that after the power source is input, noise elimination, surge absorption treatment, input voltage, and current value are monitored and indicated and the current is cut off at abnormal or warning alarm is produced.
Abstract:
A reduced pressure drop debris filter bottom nozzle for use in a fuel assembly of a nuclear reactor includes a plate member formed with a plurality of first flow holes and a plurality of second flow holes. The first flow holes are oblong in cross section and may be of an oval configuration. The first flow holes each have in cross section a major axis and a minor axis, the major axis being longer than the minor axis. The second flow holes are circular in cross section and may have a diameter substantially equal to the minor axis of the first flow holes. The bottom nozzle also features support ligaments that extend between the first flow holes and that are axially aligned with fuel rods within the fuel assembly.
Abstract:
In one embodiment, a button mapping method comprising comparing an image difference between images before and after a keyboard event, the images including a first and second version of buttons in a menu, respectively; constructing by the processor a button map based on the comparison, the button map comprising button information for at least two buttons in the menu; receiving one or more selection signals corresponding to one or more non-keyboard events; and translating the one or more selection signals into one or more keyboard events based on the button map, wherein the button in the menu is selected based on the translation.
Abstract:
A spacer grid for a nuclear fuel assembly that exhibits increased crush strength. Each grid strap at the ligaments that support fuel rods has a spring or dimple to support the fuel rods under anticipated external loads during shipping and handling or in a seismic event. One or more elongated embossed ribs are provided on each of the fuel rod grid strap support ligaments to increase its moment of inertia by forming various shapes on the ligaments of the grid strap. Preferably, the ribs have a streamlined shape to prevent any excessive pressure drop. In this manner, the crush strength of a conventional short grid strap is increased without meaningful additional manufacturing costs or adverse effects to the neutron economy of the grid.