Korea Atomic Energy Research Institute

Korea Hydro Nuclear Power Co., Ltd.

Yung-Zun Cho

In-Tae Kim

Hwan Seo Park

Hee-Chul Yang

Hee-Chul Eun

Young-Hwan Kim

Geun-Il Park

Jung Hoon Choi

Hansoo Lee

Byung-Gil Ahn

Han-Soo Lee

Jin-Mok Hur

Hwan-Young Kim

Hwan-Seo Park

JunHong Kim

Young-Soon Lee

Tae-Kyo Lee

A mechanical decladder for a spent nuclear fuel rod-cut includes an opening and closing unit configured to open and close an outlet of a basket into which the nuclear fuel rod-cut is loaded, a supporter on which the nuclear fuel rod-cut discharged from the outlet of the basket is seated, a hydraulic cylinder module configured to move the nuclear fuel rod-cut seated on the supporter; and a cutting module for slitting the nuclear fuel rod-cut while the nuclear fuel rod-cut is being moved by the hydraulic cylinder module. The opening and closing unit opens and closes the outlet of the basket in conjunction with a movement of the hydraulic cylinder module.

Mechanical decladder for spent nuclear rod-cuts

There are provided an apparatus and method for separating radioactive nuclides from a waste salt and recovering a refined salt, which are able to maximize process efficiency and operating efficiency of a process of regenerating a waste salt produced during a pyrochemical process of used nuclear fuel by converting the waste salt into a thermally stable form and distilling the waste salt under a reduced pressure using a single apparatus having two top covers which are mountable to replace radioactive nuclides included in the waste salt, and highly improve applicability and utility in a remote operation facility for disposal of a radioactive waste by further simplifying operation/handling compared with conventional processes.

Apparatus and method for separating radioactive nuclides and recovering refined salt from LiCl waste salt or LiCl-KCI eutectic waste salt

The present invention relates to a method and apparatus for solidifying radioactive waste accompanying chlorine recycling or radioactive iodine removal. The present invention provide a method and apparatus for treating radioactive waste composed of volatile metal halide with high corrosiveness at a high temperature through a solidifying system including crushing, mixing/dehalogenating and sintering. In the inventive method and apparatus for solidifying radioactive waste, a dechlorination process by using a dehalogenation material is performed on highly corrosive metal salt under an oxidizing atmosphere by using a method of controlling a temperature on the surface of a reactor, and solidification is carried out by removing radioactive iodine while reusing chlorine contained in an exhaust gas. Accordingly, the generated amount of total waste can be reduced, and therefore the inventive method and apparatus can be usefully used in preparing a solidified body with high durability.

Solidification method of radioactive waste accompanying chloride recycling or radioactive iodide removing and the device thereof

A reuse apparatus of eutectic salt waste produced in an electro refining process and a method thereof is a technology that in order to collect the eutectic salt of the eutectic salt waste, oxidizes/precipitates nuclides (rare earth and TRU) within the eutectic salt waste, an oxygen dispersing method is used to perform a layer separation into the eutectic salt layer and the precipitate layer. Then, the precipitate layer and eutectic salt layer are separated and collected, so that the eutectic salt layer is directly reused and the eutectic salt within the precipitates is reused by separating and collecting it using distillation/condensation processes. The reuse apparatus of the eutectic salt waste and a method thereof thereby increases the collecting efficiency of the eutectic salt and allows the compositions of the collected eutectic salt to have the same compositions as the eutectic salt used in the electro refining process.

Reuse method of radioactive waste salt and the apparatus thereof

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Daejeon, South Korea

Yung-Zun Cho