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: Provided is a method and apparatus for detecting an intrusion in a cloud computing service. An elementary detector may monitor a virtual machine provided by a cloud computing service, and may generate a raw alert based on a result of the monitoring. An intrusion detection system (IDS) dispatcher may determine occurrence of an intrusion into the cloud computing service by comparing the raw alert and a local database. The IDS dispatcher may generate a hyper alert when it is determined that the intrusion has occurred. An intrusion detection system (IDS) manager may determine the occurrence of the intrusion by comparing the hyper alert and a global database.

Abstract: Provided are a method and apparatus for data sharing based on an individual environment setup. An access control unit authenticates the user having requested a data object, and extracts the individual environment setup of the user. The individual environment setup includes a list of data objects possessed by the user and access information on each data object in the list. A service unit acquires the data object requested from a distributed file system unit using the individual environment setup, and provides the requested data object to the user.

Abstract: Provided is a method and system for assigning a suitable right to a user through a security policy based access control in a computing service. A collaborative service server may authenticate a user through a cloud service server, and may issue an access token including user authentication information and user right information. The cloud service server may compare information associated with the access token and an access control list and may determine whether to authorize an access of the user to the service based on the comparison result.

Abstract: Provided is a method and apparatus for security in a cloud computing service. A service integration unit provides various cloud services to a terminal over a personal virtual network. An authentication unit performs authentication on a user of the terminal through redirection in the service integration unit. The service integration unit generates a virtual machine for providing a cloud service requested by the terminal on a service providing unit. The service providing unit provides the cloud service to the terminal authenticated by the user.

Abstract: Provided is a method and apparatus for detecting an intrusion in a cloud computing service. An elementary detector may monitor a virtual machine provided by a cloud computing service, and may generate a raw alert based on a result of the monitoring. An intrusion detection system (IDS) dispatcher may determine occurrence of an intrusion into the cloud computing service by comparing the raw alert and a local database. The IDS dispatcher may generate a hyper alert when it is determined that the intrusion has occurred. An intrusion detection system (IDS) manager may determine the occurrence of the intrusion by comparing the hyper alert and a global database.

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: Provided are a virtual aggregation gateway and a method of providing an N-screen service using the virtual aggregation gateway. The virtual aggregation gateway may register, to a first terminal, a cloud server that provides a cloud service. The virtual aggregation gateway may access content of the cloud server using registration information provided from the first terminal. When a request for content is received from the second terminal, the virtual aggregation gateway may verify whether the content is shared by the second terminal, and may transform the content to be suitable for the second terminal The virtual aggregation gateway may provide the transformed content to the second terminal.

Abstract: The present invention relates to a coating method for the preparation of a coated nuclear fuel. Particularly, the present invention relates to the coating method of nuclear fuel surface with more than two coated layers of carbides, borides or nitrides and their compounds comprising deposition or permeation steps of i) elements or mixture that can form carbides, borides or nitrides and ii) a layer of pyrolytic carbon or boron prepared by chemical vapor deposition(CVD) or sputtering in sequence or in reverse sequence, or nitrogen prepared by gas permeation in sequence, on the nuclear fuel surface. The coated layers are formed with carbides, borides, nitrides or their mixture at high temperature and pressure by a combustion synthesis.