Abstract: Disclosed are a nuclear fuel pellet having enhanced thermal conductivity and a method of manufacturing the same, the method including (a) a step of manufacturing a mixture including a nuclear fuel oxide powder and a thermally conductive plate-shaped metal powder; and (b) a step of molding and then heat-treating the thermally conductive plate-shaped metal powder to have an orientation in a horizontal direction in the mixture, thereby forming a pellet.

Abstract: A method of a nuclear fuel pellet including a thermal conductive metal and a nuclear fuel pellet prepared thereby. The method includes preparing an oxide nuclear fuel granule having about 30%-45% theoretical density, mixing the fuel granule with thermal conductive metal powder, compacting the fuel granule with which the thermal conductive metal powder is mixed to prepare a green pellet, and sintering the green pellet. In the method, the sintering may be performed under a reducing gas atmosphere that is the same as the commercial pellet preparing process. Thus, compatibility compared to existing commercial preparing processes may be superior. Also, since a liquefied oxide formation process and a reducing process are omitted, the distribution uniformity of the metal material within the pellet may be superior. Therefore, the nuclear fuel pellet in which the metal network and fine microstructure are uniformly distributed within the pellet may be prepared.

Abstract: A uranium dioxide nuclear fuel pellet has about 50 to about 400 ?M (with respect to a 3-dimentional size) microcells formed of a ceramic material having a chemical attraction with fission products generated in the nuclear fuel pellet to absorb and trap the fission products, such that the extraction of the fission product may be retrained in a normal operation condition and that the performance of the nuclear fuel may be enhanced by mitigating PCI. In addition, highly radioactive fission products including Cs and I having a large generation amount or a long half-life enough to affect the environments can be trapped in the pellet in an accident condition, without being released outside.

Abstract: Disclosed is a spinal complex cage, which includes a cage which is made of a polymeric material, and metal covers which are formed on upper and lower portions of the cage, respectively, in which couplers formed on the metal covers are coupled to coupling grooves formed in the cage, such that the metal covers are detachably coupled to the upper and lower portions of the cage. Accordingly, because the cage and the metal cover are detachably coupled to each other, the manufacturing method is simple, and the metal cover is easily coupled to or separated from the cage, such that the spinal complex cage may be variously and quickly applied even during the surgery in accordance with shapes or intervals between the vertebral bodies, and as a result, a spinal fusion rate is excellent, and the accurate and precise surgical operation is enabled.

Abstract: A display controller includes a local contrast enhancement circuit that includes a plurality of scale circuits. Each scale circuit includes a block separation circuit configured to divide input display data into sub blocks, a calculation circuit configured to calculate a feature value that characterizes each of the sub blocks, and a storage device configured to store the feature value. The number and size of the sub blocks differ among the scale circuits.

Abstract: Disclosed is a uranium dioxide nuclear fuel pellet, which includes metallic microcell partitions having a high protection capacity for fission products and a high thermal conductivity simultaneously. These metal microcell partitions are arranged in the nuclear fuel pellet to trap fission products. Further disclosed is a method of making the uranium dioxide nuclear fuel pellet. The method includes providing a mixture of uranium dioxide powder and additive powder of Cr-containing compound or Mo-containing compound; compressing the powder mixture to form a green pellet; and then sintering the green pellet under reducing gas environment to form the metallic microcell partitions.

Abstract: A method of a nuclear fuel pellet including a thermal conductive metal and a nuclear fuel pellet prepared thereby. The method includes preparing an oxide nuclear fuel granule having about 30%-45% theoretical density, mixing the fuel granule with thermal conductive metal powder, compacting the fuel granule with which the thermal conductive metal powder is mixed to prepare a green pellet, and sintering the green pellet. In the method, the sintering may be performed under a reducing gas atmosphere that is the same as the commercial pellet preparing process. Thus, compatibility compared to existing commercial preparing processes may be superior. Also, since a liquefied oxide formation process and a reducing process are omitted, the distribution uniformity of the metal material within the pellet may be superior. Therefore, the nuclear fuel pellet in which the metal network and fine microstructure are uniformly distributed within the pellet may be prepared.

Abstract: A display controller includes a local contrast enhancement circuit that includes a plurality of scale circuits. Each scale circuit includes a block separation circuit configured to divide input display data into sub blocks, a calculation circuit configured to calculate a feature value that characterizes each of the sub blocks, and a storage device configured to store the feature value. The number and size of the sub blocks differ among the scale circuits.

Abstract: Provided are a system and method for a video call. The system for a video call includes one or more terminals configured to transmit images obtained by capturing video call users, and a video call control server configured to generate a combined image by combining the images transmitted by the one or more terminals, and transmit the combined image to the terminals. Here, the respective images are rotated according to information on orientations sensed by the terminals, and combined into the combined image.

Abstract: An image processor includes a gain controller and a data processing block. The gain controller is configured to adjust an initial gain value of a first tone mapping function corresponding to first image data using a dimming step value until the initial gain value is the same as a target gain value of a second tone mapping function corresponding to second image data. The data processing block is configured to generate a final tone mapping function using a reference function and a third tone mapping function generated based on the adjusted initial gain value. The first image data is data before a scene change occurs, and the second image data is data after the scene change occurs. The tone mapping function is a first-order function generated using the adjusted initial gain value. An order of the reference function is higher than an order of the tone mapping function.

Abstract: Provided are a method of controlling the compositional gradient and solubility of doped-additives at grain boundaries during sintering of a uranium-based oxide green pellet including the additives, and a method of manufacturing a sintered nuclear fuel pellet having a large grain size using the same. The grain boundary solubility of the doped-additives is maintained at a certain level by stepwise varying of an oxygen partial pressure during isothermal sintering of a uranium-based oxide green pellet including the additives. The method of manufacturing a sintered nuclear fuel pellet having a large grain size includes preparing additive mixed uranium oxide powder, forming an additive mixed uranium oxide green pellet using the mixed powder, heating the green pellet to a sintering temperature in a gas atmosphere having a low oxygen partial pressure, and sintering while a sintering gas atmosphere is changed to stepwise increase an oxygen partial pressure at the isothermal sintering temperature.

Abstract: Provided are an apparatus for a multi-party video call, a server for controlling a multi-party video call, and a method of displaying a multi-party image. The apparatus for a multi-party video call includes a receiver module configured to receive a composite image of multi-party video call participants from a server, an image separating module configured to separate images of the respective multi-party video call participants from the composite image received by the receiver module, and a display module configured to arrange the separated images according to a predetermined layout and display the separated images on a screen.

Abstract: A method of establishing a secure session between a client and a server by a network node accessed by the client and the server includes receiving, by the network node, a client side random number generated by the client; generating, by the network node, a server side random number in response to reception of the client side random number; transmitting, by the network node, the server side random number to the client such that the client calculates a secret key of a secure session to be established between the client and the server; receiving, by the network node, a client side key, used by the client to calculate the secret key, from the client; and transmitting, by the network node, the client side random number, the server side random number, and the client side key to the server such that the server calculates the secret key.

Abstract: UO2 nuclear fuel pellets are fabricated by adding additive powder comprising Mn compound and Al compound into UO2 powder.

Abstract: Provided are a system and method for a video call. The system for a video call includes one or more terminals configured to transmit images obtained by capturing video call users, and a video call control server configured to generate a combined image by combining the images transmitted by the one or more terminals, and transmit the combined image to the terminals. Here, the respective images are rotated according to information on postures sensed by the terminals and combined into the combined image.

Abstract: A uranium dioxide nuclear fuel pellet has about 50 to about 400 ?M (with respect to a 3-dimentional size) microcells formed of a ceramic material having a chemical attraction with fission products generated in the nuclear fuel pellet to absorb and trap the fission products, such that the extraction of the fission product may be retrained in a normal operation condition and that the performance of the nuclear fuel may be enhanced by mitigating PCI. In addition, highly radioactive fission products including Cs and I having a large generation amount or a long half-life enough to affect the environments can be trapped in the pellet in an accident condition, without being released outside.

Abstract: A uranium dioxide nuclear fuel pellet includes metallic microcells having a high protection capacity for fission products and a high thermal conductivity simultaneously arranged in the nuclear fuel pellet to trap fission products, such that extraction of fission products may be restrained in a normal operation condition and that the temperature of a nuclear fuel may be lowered to enhance the performance of the nuclear fuel, only to restrain extraction of radioactive fission products toward the environment in an accident condition to enhance a stability of the nuclear fuel pellet, and a fabricating method thereof.

Abstract: Provided are an apparatus for a multi-party video call, a server for controlling a multi-party video call, and a method of displaying a multi-party image. The apparatus for a multi-party video call includes a receiver module configured to receive a composite image of multi-party video call participants from a server, an image separating module configured to separate images of the respective multi-party video call participants from the composite image received by the receiver module, and a display module configured to arrange the separated images according to a predetermined layout and display the separated images on a screen.

Abstract: A method for fabricating a sintered annular nuclear fuel pellet includes molding nuclear fuel powder or granule, an oxide of a fissile element (M), to fabricate an annular nuclear fuel green body. A rod-like shaped structure is inserted into the annular nuclear fuel green body and sintered in a slight oxidizing gas atmosphere such that the oxide of the fissile element has a balanced O/M ratio higher than a desired O/M ratio (oxygen/fissile element) of a final sintered annular nuclear fuel pellet, while being maintained in a cubic phase. The sintered annular nuclear fuel pellet is then reduced in a reductive gas atmosphere so as to have the desired O/M ratio in the state that the rod-like shaped structure is inserted.

Abstract: A method for fabricating a sintered annular nuclear fuel pellet includes: molding nuclear fuel powder or granules to fabricate an annular nuclear fuel green body; inserting a rod-like shaped structure into the annular nuclear fuel green body; sintering the rod-like shaped structure-inserted annular nuclear fuel green body in a reductive gas atmosphere; and separating the sintered annular nuclear fuel pellet from the rod-like shaped structure.