Korea Atomic Energy Research Institute

Korea Hydro Nuclear Power Co., Ltd.

Jae Hwan Yang

Geun-Il Park

Jang Jin Park

Jin-Myeong Shin

Youngja Kim

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 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.

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Daejeon, South Korea

Jae Hwan Yang