Abstract: A method for registering a wireless device by a terminal in a wireless communication system is provided. The method includes obtaining connection information for the wireless device by scanning a recognition code of the wireless device in a first mode, transitioning to a second mode based on the connection information and receiving a connection request from the wireless device, performing a connection operation to the wireless device to transmit network access information to the wireless device, and transitioning to the first mode, and registering the wireless device upon detecting connection of the wireless device to a network in the first mode.

Abstract: The present disclosure relates to a diagnostic cartridge for immunodiagnosis, and a reader and a diagnostic system using the same. A diagnostic cartridge, including the diagnostic pad and the color reaction pad, is provided to detect a color reaction and a fluorescence reaction through the single diagnostic cartridge.

Abstract: Disclosed herein is a method for manufacturing oxide fuel pellets. The method for manufacturing the oxide fuel pellets includes (step 1) preparing nuclear fuel powder containing uranium dioxide (UO2+x, x=0 to 0.20), (step 2) compacting the nuclear fuel powder prepared in step 1 to manufacture green pellets, sintering the green pellets manufactured in step 2 at a temperature of about 1,200° C. to about 1,400° C. by using an atmosphere gas, and reducing the green pellets sintered in step 3 at a temperature of about 800° C. to about 1,000° C. by using a reducing atmosphere gas. The method for manufacturing the oxide fuel pellets according to the present invention performs the sintering at a low temperature of about 1,200° C. to 1,400° C. to manufacture economical and safe oxide fuel pellets that are adequate for the nuclear fuel specification.

Abstract: A method for fabricating porous UO2 sintered pellets to be fed into the electrolytic reduction process for the purpose of metallic nuclear fuel recovery is provided, which includes forming a powder containing U3O8 by oxidizing spent nuclear fuel containing uranium dioxide (UO2) (step 1), fabricating green pellets by compacting the powder formed in step 1 (step 2), fabricating UO2+x sintered pellets by sintering the porous U3O8 green pellets fabricated in step 2 at 1200 to 1600° C., in an atmospheric gas (step 3), and forming UO2 sintered pellets by cooling the UO2+x sintered pellets to room temperature, and reduction the same at 1000 to 1400° C., in a reducing atmosphere (step 4).

Abstract: Disclosed herein is a method for manufacturing oxide fuel pellets. The method for manufacturing the oxide fuel pellets includes (step 1) preparing nuclear fuel powder containing uranium dioxide (UO2+x, x=0 to 0.20), (step 2) compacting the nuclear fuel powder prepared in step 1 to manufacture green pellets, sintering the green pellets manufactured in step 2 at a temperature of about 1,200° C. to about 1,400° C. by using an atmosphere gas, and reducing the green pellets sintered in step 3 at a temperature of about 800° C. to about 1,000° C. by using a reducing atmosphere gas. The method for manufacturing the oxide fuel pellets according to the present invention performs the sintering at a low temperature of about 1,200° C. to 1,400° C. to manufacture economical and safe oxide fuel pellets that are adequate for the nuclear fuel specification.

Abstract: Porous UO2 sintered pellets to be fed into an electrolytic reduction process for the purpose of metallic nuclear fuel recovery, include one or more hollow spaces formed from the surfaces toward the interiors thereof. When the porous UO2 sintered pellets are used in the electrolytic reduction process, the efficiency increases.

Abstract: Porous UO2 sintered pellets to be fed into an electrolytic reduction process for the purpose of metallic nuclear fuel recovery, include one or more hollow spaces formed from the surfaces toward the interiors thereof. When the porous UO2 sintered pellets are used in the electrolytic reduction process, the efficiency increases.

Abstract: A neutron coincidence counter for non-destructive accounting for a nuclear material according to the present invention comprises an outer case, neutron detectors mounted in the outer case while being surrounded by a moderator, and a basket horizontally movable in the outer case so as to be exposed outside the outer case and having a cavity for receiving a sample container therein. Further, a neutron coincidence counter for non-destructive accounting for a nuclear material according to the present invention comprises an outer case, neutron detectors mounted in the outer case while being surrounded by a moderator, a basket movable in the outer case so as to be exposed outside the outer case and having a cavity for receiving a sample container therein, and an external signal analyzer connected to the detectors through an electrically conductive path.