Radioactive cesium is a heat generated and semi-volitile nuclide in spent nuclear fuel (SNF). It is released gasous phase by head-end treatment which is a pretreatment of pyroprocessing. One of the capturing methods of gasous radioactive cesium is using zeolite. After ion-exchanged zeolite, it is transformed to ceramic waste form which is durable ceramic structure by heat treatment. Various ceramic wasteforms for Cs immobilization have been researched such as cesium aluminosilicate (CsAlSi2O6), cesium zirconium phosphate (CsZr2(PO4)3), cesium titanate (CsxAlxTi8-xO16, Cs2TiNb6O18) and CsZr0.5W1.5O6. The cesium pollucite is composed to aluminosilicate framework and cesium ion incorporated in matrix materials lattices. Many researchers are reported that the pollucite have high chemical durability. In this study, the Cesium pollucite was fabricated using mixtures of aluminosilicate denoted Absorbent product (AP) and Cs2CO3 by calcination and pelletized by cold pressing. The characterization of fabricated pollucite powder and pellets was analyzed by XRD, TGA, SEM, SEMEDS and XRF. The chemical durability of pollucite powder was evaulated by PCT-A and ICP-MS and OES. Thus, the optimal pressure condition without breaking the pellets which is low Cs2O/AP ratio and pelletizing pressure was selected. The long-term leaching test was performed using MCC-1 method for 28 days with the fabricated pollucite pellets. The leachate of leaching test was allard groundwaster and Deionized water and replaced 5 contact periods which is 3 hours, 3 days, 7 days, 14 days and 28 days and analyzed by ICPMS. The leaching rate was shown two stages. The first stage was rapid and relatively large amount of nuclides were leached. The leaching rate was decreased in the second stage. The fractional release rate of this study was shown same trend. These results were similar to previous studies.

수은의 배출로부터 국민의 건강과 환경을 보호하기 위하여 국제수은협약(Minamata Convention on Mercury)이 2013년도에 채택되었다. Article 11에서는 수은폐기물을 수은 오염, 함유, 구성 폐기물 등 총 3가지 종류로 구분하여 정의하고 있다. 현재 국내법 체계상 수은폐기물은 따로 분류 및 처리되고 있지 않은 상황이다. 국내 수은폐기물은 발생원에 따라 넓은 농도범위의 수은을 포함하고 있다. 산업시설에서 발생한 수은폐기물은 지정 폐기물로 분류되어 폐기물관리법에서 지정하고 있는 고형화 처리 후 매립되고 있다. 매립된 고농도 수은 함유 폐기물은 장기간에 걸쳐 환경에 노출되었을 때 시멘트 고화체로부터 고농도 수은 함유 침출수가 유출되어 2차 오염원이 발생할 가능성이 높다. 그러므로 본 연구에서는 고형화 처리를 거쳐 매립된 수은폐기물이 매립지에 장기간 존재하였을 때 환경에 미칠 영향을 알아보고자 하였다. 또한 수은폐기물의 처리방법으로써 고형화 처리법이 적절한 방법인지 알아보기 위해 장기용출 시험법을 적용해보았다. 대상 시료로써 국내 산업시설 발생 폐슬러지 및 원소수은을 사용하였다. 시멘트 고화체 제작을 위해 현재 국내 폐기물관리법에 명시된 고형화물 1 m³ 당 시멘트 150 kg 이상 첨가기준 및 28일의 양생기간을 준수하였다. 또한 장기용출 실험의 용출용매로써 pH 4, 7, 10의 버퍼용액을 사용하였다. 용출용매는 1, 3, 7, 28일 주기로 교체해 주었다. 용출액 수은 함량분석 결과 초기단계에 용출시험 기준치 수은항목 0.005 mg/L 이상의 수은이 용출되었음을 확인하였다. 28일 이후에 용출되는 수은량이 점차 감소하는 추세를 나타내었으나 여전히 수은이 용출되는 것을 확인하였다. 이러한 실험결과로 보아 고농도 수은폐기물을 대상으로 고형화 처리를 진행하는 것은 적절하지 않은 방법으로 판단된다. 그러므로 고농도 수은폐기물은 고형화 처리 이외의 기술을 적용시킬 필요가 있으며 고농도의 수은을 포함하고 있는 수은폐기물의 매립을 제한할 필요가 있다고 판단된다.

Lead leached out from the metal lead-sinker attached to fishing nets or contained in ropes are likely to cause the environmental contamination, consequently, resulting in ecotoxicity. However, it is very difficult to find out the data on the disposal reality of fishing nets, lead-containing form of/in fishing net and its content. In previous studies, we presented the containing form of lead and the lead concentration leached out by the containing forms. As a result, the leaching concentration of lead was the highest under the supposition condition of lead-sinker deposited on sandy tidal flat. In this study, as a subsequent study, we investigated long-term leaching characteristics from lead-sinker deposited on sandy tidal flat. We used a serial batch leaching experiment to investigate the long-term leaching characteristics, and the experimental conditions were as follows; solid to liquid ratio 1:20, shaking time 24 hours (repetition of 7 times), room temperature, and shaking rate 170 rpm. As a result, lead leaching concentration after shaking for 24 hours was 0.215 mg/L, showing the highest leaching concentration, and then the leaching concentrations between 2-7 times were greatly decreased. Analysis result by Visual Minteq 3.1 said most of the leached lead component could be extracted as crystal such as Anglesite (PbSO4), Cerrusite (PbCO3), Cotunnite (PbCl2), and Pb(OH)2 by sulfate and carbonate in seawater.

Radioactive waste repositories require long-term durability of concrete in contact with ground water. However, contact of the ground water leads to Ca2+ leaching process between pore water and pure water. Therefore, this study is aimed at investigating the effect of the leaching process of concrete based on their physical properties and durabilities. According to results, as the leaching period became longer, the pore volume is greatly increased and the chloride diffusion coefficient of the degraded concrete increased with leaching process.