Abstract: The present disclosure relates to a cathode active material for an all-solid-state battery with a controlled particle size and a method for preparing the same. In particular, the cathode active material includes lithium and a transition metal, wherein the cathode active material has a single peak in the range of 1 ?m to 10 ?m as a result of particle size distribution (PSD) analysis.

Abstract: An electronic price indicator according to an embodiment includes a display displaying product information, an NFC module configured to communicate with a user terminal, a Bluetooth module configured to communicate with the user terminal, and a processor configured to control the display to display the product information received from the user terminal through the Bluetooth module. The processor is further configured to release a sleep mode when receiving an interrupt from the user terminal through the NFC module, and perform Bluetooth communication with the user terminal by initiating a scan for a predetermined period of time to receive an advertising signal from the user terminal.

Abstract: Provided are an apparatus and method for manufacturing a solidified salt that is easy to treat in size and shape by using a vacuum transfer and a dual vessel. In the apparatus for quantitative solidification of a molten salt, a molten salt is introduced into a first vessel, and a second vessel is disposed inside the first vessel and quantitatively supplied with the molten salt. A molten-salt transferring unit quantitatively transfers the molten salt from the first vessel to the second vessel by vacuum pressure. A valve controls a discharge of the molten salt from the second vessel. A mold receives the molten salt from the second vessel and solidifies the molten salt. Accordingly, the molten salt can be stably discharged to the mold by quantitatively transferring the molten salt at vacuum pressure within the dual vessel, and a predetermined size and shape of the solidified salt can be manufactured, thereby processing and collecting the solidified salt safely.

Abstract: Disclosed relates to a method for preparing tantalum or niobium powders used for manufacturing capacitors in an electrolytic reducing reactor including an anode, a cathode and a molten salt, the method comprising: obtaining a tantalum or niobium oxide, expressed by Ta2O(5-y) or Nb2O(5-y) where y=2.5 to 4.

Abstract: Provided are an apparatus and method for manufacturing a solidified salt that is easy to treat in size and shape by using a vacuum transfer and a dual vessel. In the apparatus for quantitative solidification of a molten salt, a molten salt is introduced into a first vessel, and a second vessel is disposed inside the first vessel and quantitatively supplied with the molten salt. A molten-salt transferring unit quantitatively transfers the molten salt from the first vessel to the second vessel by vacuum pressure. A valve controls a discharge of the molten salt from the second vessel. A mold receives the molten salt from the second vessel and solidifies the molten salt. Accordingly, the molten salt can be stably discharged to the mold by quantitatively transferring the molten salt at vacuum pressure within the dual vessel, and a predetermined size and shape of the solidified salt can be manufactured, thereby processing and collecting the solidified salt safely.

Abstract: Disclosed are a method of reducing spent oxides nuclear fuel to nuclear-fuel metal, in which metal oxides are reduced to metals using an electrochemical reduction device with LiCl—Li2O salt as an electrolyte, a cathode electrode assembly used in the method, and a reduction device including the cathode electrode assembly. The method is advantageous in that the process of reducing the spent oxide nuclear fuel to the nuclear-fuel metal and another process of recovering Li are united to simplify the whole processes, direct use of high oxidative Li metals is excluded to secure safety, and conversion efficiency of the spent oxide nuclear fuel is 99% or more.

Abstract: Disclosed is a device for metallizing uranium oxide and recovering uranium, which reacts uranium oxide with a lithium metal to product uranium metal powder, and filters the resulting product using a porous filter to separate the uranium metal powder from lithium chloride molten liquid to recover the uranium metal powder. The device includes a heating furnace including at least one first heating unit, and a reactor includes a reaction vessel having a discharging valve hole located at the center of a bottom thereof and a conical bottom tapered to the discharging valve hole, a sealing lid for sealing the reaction vessel airtight, an argon gas inlet port for feeding argon gas into the reactor therethrough, and an argon gas outlet port for venting argon gas from the reactor therethrough. A valve assembly controls the discharging valve hole of the reaction vessel, and a plurality of agitators mix a mixture in the reactor.

Abstract: Disclosed is a device for metallizing uranium oxide and recovering uranium, which reacts uranium oxide with a lithium metal to product uranium metal powder, and filters the resulting product using a porous filter to separate the uranium metal powder from lithium chloride molten liquid to recover the uranium metal powder. The device includes a heating furnace including at least one first heating unit, and a reactor includes a reaction vessel having a discharging valve hole located at the center of a bottom thereof and a conical bottom tapered to the discharging valve hole, a sealing lid for sealing the reaction vessel airtight, an argon gas inlet port for feeding argon gas into the reactor therethrough, and an argon gas outlet port for venting argon gas from the reactor therethrough. A valve assembly controls the discharging valve hole of the reaction vessel, and a plurality of agitators mix a mixture in the reactor.

Abstract: Disclosed are a method of reducing spent oxides nuclear fuel to nuclear-fuel metal, in which metal oxides are reduced to metals using an electrochemical reduction device with LiCl—Li2O salt as an electrolyte, a cathode electrode assembly used in the method, and a reduction device including the cathode electrode assembly. The method is advantageous in that the process of reducing the spent oxide nuclear fuel to the nuclear-fuel metal and another process of recovering Li are united to simplify the whole processes, direct use of high oxidative Li metals is excluded to secure safety, and conversion efficiency of the spent oxide nuclear fuel is 99% or more.