Abstract: The present disclosure relates to a pellet containing an oxide additive to improve a nuclear-fission-gas-adsorption ability of a uranium-dioxide pellet used as nuclear fuel and increase the grain size thereof, and to a method of manufacturing the same. A La2O3—Al2O3—SiO2 sintering additive is added to uranium dioxide so that mass movement is accelerated due to the liquid phase generated during sintering of the uranium-dioxide pellet, which promotes the growth of grains thereof. Further, since less volatilization occurs during sintering due to the low vapor pressure of the liquid phase, efficient additive performance is exhibited, so the liquid phase surrounding the grain boundary effectively adsorbs cesium, which is a nuclear fission gas.

Abstract: The present disclosure relates to a display device, and the display device according to an embodiment includes: a substrate including a display area and a peripheral area; a plurality of light-emitting elements positioned in a display area; a plurality of pixel circuits connected to a plurality of light-emitting elements, respectively; a sensor positioned on the peripheral area of the substrate; a leakage current detecting circuit connected to the sensor; and a light emitting wiring connected to the leakage current detecting circuit and connected to at least one of the plurality of light-emitting elements, wherein the sensor includes a first sensor and the first sensor includes a first sensing transistor, and a first conductive pattern spaced apart from the channel of the first sensing transistor, and the first conductive pattern is positioned in the same layer as at least one of a plurality of layers configuring the transistor.

Abstract: Provided is a display device comprising a display area including a plurality of pixels and a pad area disposed outside the display area, wherein the pad area includes a plurality of pads, and anchor structures positioned between two adjacent pads among the plurality of pads, the pad area includes a substrate, and at least one insulation layer that is positioned on the substrate and includes a first opening positioned between the two adjacent pads when viewed on the cross-section, and the anchor structure includes a first insulation layer that is positioned in the first opening, and does not overlap the pad.

Abstract: An organic light-emitting display device comprises a first thin-film transistor disposed on a substrate; and a second thin-film transistor disposed on the substrate and spaced apart from the first thin-film transistor. The first thin-film transistor comprises a first semiconductor layer, a first conductive layer disposed on the first semiconductor layer and that overlaps the first semiconductor layer, and a first insulating layer disposed between the first semiconductor layer and the first conductive layer. The second thin-film transistor comprises a second semiconductor layer, and a second conductive layer disposed on the second semiconductor layer and that overlaps the second semiconductor layer.

Abstract: Disclosed is a graft copolymer, and a graft copolymer including a rubbery polymer, wherein the rubbery polymer includes a conjugated diene-based monomer unit and a soft domain, the graft copolymer includes an alkyl (meth)acrylate-based monomer unit, an aromatic vinyl-based monomer unit, and an alkali metal sulfonate-based monomer unit, the soft domain is formed by including a mineral-based oil, the mineral-based oil includes 70 wt % to 100 wt % of a mineral oil and 0 wt % to 30 wt % of a silicone-based oil, the mineral-based oil is included in 0.2 parts by weight to 0.5 parts by weight based on 100 parts by weight of the rubbery polymer, and the alkali metal sulfonate-based monomer unit is included in 0.8 wt % to 1.5 wt % based on the graft copolymer, a method for preparing the same, and a resin composition including the same.

Abstract: Embodiments of the disclosure relate to a ferritic alloy having excellent ability to withstand nuclear power plant accidents and a method of manufacturing a nuclear fuel cladding tube using the same. The alloy includes iron (Fe), aluminum (Al), chromium (Cr), and nickel (Ni). The nickel (Ni) may be included 0.5 to 10 wt % based on a total amount of the alloy. The chromium may be included 13 to 18 wt % based on the total amount of the alloy. The aluminum may be included 5 to 7 wt % based on the total amount of the alloy.

Abstract: An organic light-emitting display device comprises a first thin-film transistor disposed on a substrate; and a second thin-film transistor disposed on the substrate and spaced apart from the first thin-film transistor. The first thin-film transistor comprises a first semiconductor layer, a first conductive layer disposed on the first semiconductor layer and that overlaps the first semiconductor layer, and a first insulating layer disposed between the first semiconductor layer and the first conductive layer. The second thin-film transistor comprises a second semiconductor layer, and a second conductive layer disposed on the second semiconductor layer and that overlaps the second semiconductor layer.

Abstract: The present invention relates to a communication node, a method of operating the same, and a collaborative system.

Abstract: A recycled polishing pad includes an upper layer pad and a supplementary pad. The upper layer pad includes a first surface and a second surface opposite to the first surface. The first surface has a plurality of first grooves and the second surface has a plurality of second grooves. The upper layer pad further includes a connecting body connecting the first grooves and the second grooves. The supplementary pad is in contact with the second surface of the upper layer pad. A depth of each of the first grooves is less than a depth of each of the second grooves.

Abstract: A power inverter may include a housing including an arrangement space having a capacitor arranged in a center portion thereof, a pair of cooling spaces formed on opposite sides of the arrangement space and include first and second cooling spaces, a cooling passage communicating first ends of the pair of cooling spaces with each other, and a pair of through holes respectively fluidically-connecting second ends of the pair of cooling spaces to outside of the power inverter apparatus; a first cooling plate coupled to the first cooling space to seal the first cooling space thereby; a second cooling plate coupled to the second cooling space and provided with a pair of flow holes; a first power module contacting with the first cooling plate; a second power module contacting with the second cooling plate; an extrusion cooler contacting with the second power module; and a third power module contacting with the extrusion cooler.

Abstract: Provided is a nuclear-fuel sintered pellet based on oxide in which a plate-type fine precipitate material in a base of a sintered pellet of uranium dioxide, used as nuclear fuel in nuclear power plants, is uniformly dispersed in a matrix of uranium dioxide fuel thereof so as to form a donut-shaped precipitate cluster, and to a method of manufacturing the same. The plate-type fine precipitate material is uniformly precipitated in a tissue thereof or forms a donut-shaped precipitate cluster having a two-dimensional structure through dispersion to improve thermal and physical performance of the nuclear-fuel sintered pellet of uranium dioxide, whereby the creep deformation rate and thermal conductivity of the sintered pellet are improved. The nuclear-fuel sintered pellet based on oxide can reduce the Pellet-Clad Interaction (PCI) failure and the core temperature of nuclear fuel when an accident occurs, thereby significantly improving the safety of a nuclear reactor.

Abstract: Disclosed is a graft copolymer, and a graft copolymer including a rubbery polymer, wherein the rubbery polymer includes a conjugated diene-based monomer unit, and one or more compound units selected from the group consisting of compounds represented by Formula 1, wherein the graft copolymer includes an alkyl (meth)acrylate-based monomer unit and an aromatic vinyl-based monomer unit, the content of the one or more compound units selected from the group consisting of the compounds represented by Formula 1 is from 0.1 wt % to 5.0 wt % with respect to the graft copolymer, the alkyl (meth)acrylate-based monomer unit is crosslinked from a crosslinking agent, and a weight average molecular weight of the aromatic vinyl-based monomer unit is from 20,000 g/mol to 100,000 g/mol. Also disclosed is a method for preparing a graft copolymer and a resin composition including same.

Abstract: Proposed are nuclear fuel pellets showing high oxidation resistance in a steam atmosphere and a method for manufacturing same. The method includes: preparing a powder mixture by mixing a sintering additive powder including Cr2O3, MnO, and SiO2 with a uranium dioxide powder; forming a molded body by subjecting the powder mixture to compression molding; and sintering the molded body in a weak oxidative atmosphere in which an oxygen potential is ?581.9 kJ/mol to ?218.2 kJ/mol. The nuclear fuel pellets contain 0.05% to 0.16% by weight of the sintering additive composed of Cr2O3, MnO, and SiO2. A liquid phase generated during the sintering accelerates grain growth and inhibits reaction between uranium dioxide with steam by forming a film at the grain boundary of the uranium dioxide. This reduces leakage of a fission material by improving high-temperature water vapor oxidation resistance at around 1204° C. in a loss-of-coolant accident condition.

Abstract: A display device includes a substrate, a first semiconductor layer on the substrate and including an oxide semiconductor, a first gate insulating film on the first semiconductor layer, a first conductive layer on the first gate insulating film, a first interlayer insulating film on the first conductive layer, and a second conductive layer on the first interlayer insulating film and connected to the first semiconductor layer through a through-hole. The through-hole includes a first through-hole passing through the first interlayer insulating film, and a second through-hole overlapping the first through-hole and passing through the first semiconductor layer. The second conductive layer is in contact with a side surface of the first semiconductor layer exposed at the second through-hole.

Abstract: Provided is a core-shell copolymer, and in particular, a core-shell copolymer including a core and a shell surrounding the core, wherein the core includes a conjugated diene monomer-derived repeating unit, an aromatic vinyl monomer-derived repeating unit, and an aromatic (meth)acrylate monomer-derived repeating unit, the shell includes an alkyl (meth)acrylate monomer-derived repeating unit, an aromatic vinyl monomer-derived repeating unit, and an aromatic (meth)acrylate monomer-derived repeating unit, the core has a particle size of 800 ? to 900 ?, the core-shell copolymer has a particle size of 900 ? to 1000 ?, the core has a refractive index of 1.5355 to 1.5425, and the core-shell copolymer has a refractive index of 1.5415 to 1.5440.

Abstract: A method of manufacturing a zirconium alloy for a nuclear fuel cladding tube includes melting a mixture of 0.5 wt % of Nb, 0.4 wt % of Mo, 0.1 to 0.15 wt % of Cu, 0.15 to 0.2 wt % of Fe, and a balance of zirconium to prepare a melted ingot; heat treating the melted ingot at 1,000 to 1,050° C. for 30 to 40 min. followed by quenching in water to prepare a heat-treated ingot; preheating the heat-treated ingot at 630 to 650° C. for 20 to 30 min. to prepare a preheated ingot followed by hot rolling the preheated ingot at a reduction ratio of 60 to 65% to provide a hot-rolled material; thrice performing vacuum annealing followed by cold-rolling; and vacuum annealing a third cold-rolled material in a final vacuum annealing at 510 to 520° C. for 7 to 9 hrs. to provide the zirconium alloy as a cold-rolled material.

Abstract: The present disclosure relates to a pellet containing an oxide additive to improve a nuclear-fission-gas-adsorption ability of a uranium-dioxide pellet used as nuclear fuel and increase the grain size thereof, and to a method of manufacturing the same. A La2O3—Al2O3—SiO2 sintering additive is added to uranium dioxide so that mass movement is accelerated due to the liquid phase generated during sintering of the uranium-dioxide pellet, which promotes the growth of grains thereof. Further, since less volatilization occurs during sintering due to the low vapor pressure of the liquid phase, efficient additive performance is exhibited, so the liquid phase surrounding the grain boundary effectively adsorbs cesium, which is a nuclear fission gas.

Abstract: The present invention relates to a communication node, a method of operating the same, and a collaborative system.

Abstract: An organic light-emitting display device comprises a first thin-film transistor disposed on a substrate; and a second thin-film transistor disposed on the substrate and spaced apart from the first thin-film transistor. The first thin-film transistor comprises a first semiconductor layer, a first conductive layer disposed on the first semiconductor layer and that overlaps the first semiconductor layer, and a first insulating layer disposed between the first semiconductor layer and the first conductive layer. The second thin-film transistor comprises a second semiconductor layer, and a second conductive layer disposed on the second semiconductor layer and that overlaps the second semiconductor layer.

Abstract: Provided is a nuclear-fuel sintered pellet based on oxide in which a plate-type fine precipitate material in a base of a sintered pellet of uranium dioxide, used as nuclear fuel in nuclear power plants, is uniformly dispersed in a matrix of uranium dioxide fuel thereof so as to form a donut-shaped precipitate cluster, and to a method of manufacturing the same. The plate-type fine precipitate material is uniformly precipitated in a tissue thereof or forms a donut-shaped precipitate cluster having a two-dimensional structure through dispersion to improve thermal and physical performance of the nuclear-fuel sintered pellet of uranium dioxide, whereby the creep deformation rate and thermal conductivity of the sintered pellet are improved. The nuclear-fuel sintered pellet based on oxide can reduce the Pellet-Clad Interaction (PCI) failure and the core temperature of nuclear fuel when an accident occurs, thereby significantly improving the safety of a nuclear reactor.