Korea Atomic Energy Research Institute

Korea Hydro Nuclear Power Co., Ltd.

Geun-Il Park

Jang Jin Park

Jae Hwan Yang

Jin-Myeong Shin

Young-Hwan Kim

Jae-Won Lee

In-Tae Kim

Hwan Seo Park

Yung-Zun Cho

Hoo-Kun Lee

Hee-Chul Yang

Kwang-Wook Kim

Jung Hoon Choi

Eil-Hee Lee

Sang-Ho Na

Myeong-Soo Jeong

Hee-Chul Eun

Dong-Yong Chung

Bum-Hoe Kim

JunHong Kim

Tae-Kyo Lee

Youngja Kim

Han-Bum Yang

Jung-Won Lee

Kee-Chan Song

Kweon-Ho Kang

Kune-Woo Lee

Provided are an adsorbent for trapping a radioactive iodine gas generated in a process of oxidizing a nuclear fuel at a high temperature after use and a method of preparing the same, and more particularly, a radioactive iodine gas adsorbent which is formed of bismuth as a main component, thereby exhibiting an excellent radioactive iodine gas trapping capability and an excellent thermal stability after trapping, and a method of preparing the same. An adsorbent for trapping a radioactive iodine gas prepared by a method of preparing an adsorbent for trapping a radioactive iodine gas according to the present disclosure may effectively trap a radioactive iodine off-gas generated in a nuclear fuel pre-treated oxidizing process after use. Particularly, the adsorbent may trap iodine in a larger amount, which is twice or more, than a silver-containing zeolite widely used to trap a radioactive iodine gas, and the trapped iodine forms a stable compound, which is more advantageous for long-term storage. In addition, since an iodine gas is trapped using inexpensive bismuth, instead of expensive silver, in consideration of trapping a large amount of a radioactive iodine gas, the adsorbent has very excellent economic feasibility.

Porous adsorbent for trapping radioactive iodine gas and method of manufacturing the same

A voloxidizer with a double reactor for spent fuel rods decladding of the present invention includes a reactor module into which spent fuel rods are loaded, the reactor module including a reactor having a dual structure; a heater module for heating the reactor module; and a drive module for providing a driving force to the reactor module. A double reactor utilized in a voloxidizer for spent fuel rods decladding includes an internal reactor into which spent fuel rods are loaded; and an external reactor formed on an outer circumferential surface of the internal reactor. Here, a first transport part and a second transport part are formed on inside surfaces of the internal reactor and the external reactor, respectively, and the spent fuel rods are moved by the first transport part and the second transport part and oxidized when the internal reactor and the external reactor are rotated.

Voloxidizer with double reactor for spent fuel rods decladding and double reactor for use in the same

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

A method of preparing a simple ceramic ingot of a spent filter having radioactive cesium trapped therein, and a ceramic ingot of a spent filter having improved properties such as leach resistance, thermal stability, and cesium content are provided. The method includes grinding and mixing a spent filter having cesium trapped therein, adding a solidifying agent, and sintering the spent filter. The method of preparing a ceramic ingot of a spent filter can be useful in preparing the ceramic ingot of the spent filter from only the spent filter by means of simple grinding and sintering, and in preparing the ceramic ingot of the spent filter by adding a small amount of a solidifying agent. The ceramic ingot of the spent filter has a high density and improved thermal stability, and shows improved leach resistance since a leach rate of a radioactive material is remarkably low. Therefore, the spent filter having radioactive cesium trapped therein can be effectively used to prepare a stable ceramic ingot.

Ceramic ingot of spent filter having trapped radioactive cesium and method of preparing the same

A method and an apparatus are disclosed for desorbing TEDA by utilizing a fluidized bed so as to reuse a used impregnated active carbon for the purpose of removing toxic materials from a fluid. The impregnated active carbon is injected into a fluidized bed at a high temperature to carry out a desorbing process, in such a manner that TEDA and CH.sub.3 l are desorbed from the impregnated active carbon at a high temperature by utilizing the high volatility of TEDA and CH.sub.3 l. If a heated air is injected through an air inlet into the desorbing tower, the high temperature air and the used impregnated active carbon are met in a fluidized state, with the result that the active carbon with TEDA and CH.sub.3 l desorbed is discharged.

Method and apparatus for desorbing teda and methyl iodine from used

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Daejeon, South Korea

Geun-Il Park