- P-ISSN 1225-0163
- E-ISSN 2288-8985
양이온 교환능력을 갖는 합성 K-birnessite를 이용하여 수용성 우라늄 이온(UO22+)에 대한 흡착 거동을 조사하였다. K-birnessite는 KMnO4 수용액과 염산을 반응시켜 합성하였으며, 합성된 K-birnessite의구조, 비표면적 및 표면전하 등 물리화학적 특성을 규명하였다. K+ 이온은 층상구조를 갖는 MnO2 층간에존재하였으며, BET 비표면적은 38.30 m2/g이었다. 우라늄 흡착실험 조건인 pH 5.00, 이온세기 0.010M NaClO4에서 측정된 K-birnessite의 표면전하는 -1.65 C/m2이었다. 우라늄 이온은 K-birnessite 층간의 K+와이온교환 반응을 통하여 흡착하였으며, 분배계수는 일반적인 이온교환물질과 유사하였다. 본 연구결과는고준위 방사성 폐기물 지하처분장으로부터 유출될 수 있는 방사성물질의 이동을 저지하는 방법으로 활용될 수 있을 것이다.
This paper describes the sorption behaviors of aqueous uranium ions on the K-birnessite. K-birnessite was synthesized by adding a concentrated HCl to an aqueous solution of KMnO4. Physicochemical characteristics of the K-birnessite, such as structure, specific surface area and surface charge, were investigated. K-birnessite is a layered material and the K+ ions exist in the interlayer of layered K-birnessite. BET specific surface area of the K-birnessite was 38.30 m2/g. The surface charge of K-birnessite was -1.65 C/m2 at pH 5.00 and ionic strength of 0.010 M NaClO4, at which the sorption experiments of uranium ions were carried out. Uranium ions were incorporated into the interlayer of the K-birnessite by cation-exchange reaction with K+ ions, and the distribution coefficient is quite similar to those of common ion-exchange materials. The results might be applicable in the retardation of migration of radioactive materials from the underground disposal site of high-level radioactive waste.
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