Korea Atomic Energy Research Institute

Korea Hydro Nuclear Power Co., Ltd.

Jeikwon Moon

Sang Yoon Park

Chong-Hun Jung

Hui-Jun Won

In-Ho Yoon

Wangkyu Choi

Byung-Seon Choi

Jongwon Park

Hocheol Shin

Hee-Chul Yang

Jonghwan Lee

Dong Yong Chung

Kwanseong Jeong

Chang-Hoi Kim

Seonbyeong Kim

Byungseon Choi

Mansoo Choi

Dongjun Hyun

Ikjune Kim

Jun Young Jung

Geunho Kim

Jung-Sun Park

Jungsoon Park

Jun-Young Jung

Yong-Chil Seo

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.

Chemical decontamination method using chelate free chemical decontamination reagent for removal of the dense radioactive oxide layer on the metal surface

A decontamination method that includes the steps of decontaminating an object containing radioactive contaminated metals or alloys with a chemical decontamination agent including sulfuric acid (HSO) and forming a Ba or Sr precipitate by adding a Ba or Sr cation and a hydroxylion or halogen anion salts to the decontamination waste water.

Decontamination method reducing radioactive waste

Disclosed are a device and a method for controlling a motor. According to a specific embodiment of the present disclosure, an input shaft of a motor is provided with a low-resolution absolute position detector and an output shaft of the motor is provided with a low-resolution absolute position detector having a resolution greater than or equal to a reduction gear ratio. An initial offset and an offset are defined accordingly, and a high-resolution output shaft absolute position is derived from a relational expression, which is defined by an input shaft absolute position received at a predetermined time interval, a derived offset, an output shaft absolute position, and the reduction gear ratio, such that it is possible to easily detect the high-resolution output shaft absolute position by using a low-price absolute position detector without the modification or addition of an actuator.

Device and method for controlling motor

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.

Apparatus and method for simulation of dismantling operation of nuclear facility

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.

Separation and recovery device for liquid waste including radionuclide, and separation and recovery method using the same

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.

Oxidation decontamination reagent for removal of the dense radioactive oxide layer on the metal surface and oxidation decontamination method using the same

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Daejeon, South Korea

Jeikwon Moon