Abstract:
The present invention relates to a simulation of a nuclear facility dismantling operation, comprising: a database which includes information on at least one task constituting a nuclear facility dismantling operation and information on a virtual space related to the simulation of the dismantling operation; a plurality of head mounted displays (HMDs) which receives inputs of users related to the simulation; a simulation unit which generates the virtual space, transmits to the plurality of HMDs, the image of the virtual space including operator objects corresponding to each of the users of the plurality of HMDs, and processes the simulation of the dismantling operation according to the inputs received from each HMD user, wherein, when simulations which are different in at least one of the number of the users and the progress order of the tasks are processed, the simulation unit compares the simulations on the basis of at least one of the number of the users or the progress order of the tasks and displays a comparison result.
Abstract:
Provided are a separation and recovery device for a liquid waste including a radionuclide, and a separation and recovery method using the same. Specifically, the present disclosure relates to a separation and recovery device that may effectively separate a liquid waste, such as a waste detergent including a radionuclide, and simultaneously, may prevent the release of tritium and radiocarbon to the outside, and a separation and recovery method using the same.
Abstract:
A chemical decontamination reagent containing a reducing agent, a reductive metal ion, and an inorganic acid is provided to remove a radioactive oxide layer on a metal surface. The reagent can dissolve the radioactive oxide layer on the metal surface effectively at a relatively low temperature and enables a simple process of contacting the reagent to the radioactive oxide, thus economically effective in terms of cost and time required for the process. Since the decontamination does not use a conventional organic chelating agent such as oxalic acid, but the reducing agent as a main substance, the residuals of the reducing agent remained after decontamination can be decomposed and removed with an oxidizing agent. Due to the easy decomposition with the chemical decontamination reagent, secondary wastes can be minimized and the radionuclides remained in the decontamination reagent solution can be removed effectively.
Abstract:
A chemical decontamination reagent containing a reducing agent, a reductive metal ion, and an inorganic acid is provided to remove a radioactive oxide layer on a metal surface. The reagent can dissolve the radioactive oxide layer on the metal surface effectively at a relatively low temperature and enables a simple process of contacting the reagent to the radioactive oxide, thus economically effective in terms of cost and time required for the process. Since the decontamination does not use a conventional organic chelating agent such as oxalic acid, but the reducing agent as a main substance, the residuals of the reducing agent remained after decontamination can be decomposed and removed with an oxidizing agent. Due to the easy decomposition with the chemical decontamination reagent, secondary wastes can be minimized and the radionuclides remained in the decontamination reagent solution can be removed effectively.
Abstract:
The present invention provides an oxidative decontamination reagent for removal of the dense radioactive oxide layer on a metal surface, which comprises an oxidizing agent, a metal ion, and an inorganic acid. The oxidative decontamination reagent of the present invention is characteristically prepared by adding a metal ion to the conventional oxidative decontamination reagent containing an oxidizing agent and an inorganic acid. When the oxidative decontamination reagent of the present invention is used, electric potential of the metal parts of the primary system of the nuclear power plant can be regulated as passive potential owing to the added metal ion during the oxidative decontamination of the primary metal part of the nuclear power plant. Therefore, by maintaining electric potential of the metal part as passive potential, local corrosion can be inhibited and at the same time secondary waste can be significantly reduced.
Abstract:
Provided are a separation and recovery device for a liquid waste including a radionuclide, and a separation and recovery method using the same. Specifically, the present disclosure relates to a separation and recovery device that may effectively separate a liquid waste, such as a waste detergent including a radionuclide, and simultaneously, may prevent the release of tritium and radiocarbon to the outside, and a separation and recovery method using the same.