Uranium-235, used for nuclear power generation, has brought radioactive waste. It could be released into the environment during reprocessing or recycling of the spent nuclear fuel. Among the radioactive waste nuclides, I-129 occurs problems due to its long half-life (1.57×107 y) with high mobility in the environment. Therefore, it should be captured and immobilized into a geological disposal system through a stable waste form. One of the methods to capture iodine in the off-gas treatment process is to use silver loaded zeolite filter. It converts radioactive iodine into AgI, one of the most stable iodine forms in the solid state. However, it is difficult to directly dispose of AgI itself in an underground repository because of its aqueous dissolution under reducing condition with Fe2+. It must be immobilized in the matrix materials to prevent release of iodine as a result of chemical reaction. Among the matrix glasses, silver tellurite glass has been proposed. In this study, additives including Al, Bi, Pb, V, Mo, and W were added into the silver tellurite glass. The thermal properties of each matrix for radioactive iodine immobilization were evaluated. The glasses were prepared by the melt-quenching method at 800°C for 1 h. Differential scanning calorimetry (DSC) was performed to evaluate the thermal properties of the glass samples. From the study, the glass transition temperature (Tg) was increased by adding additives such as V2O5, MoO3, or WO3 in the silver tellurite glass. The relative electro-static field (REF) values of V2O5, MoO3, and WO3 are about three times higher than that of the glass network former, TeO2. It could provide sufficient electro-static field (EF) to the TeO2 interacting with the non-bridging oxygen forming Te-O-M (M = V, Mo, W) links. Therefore, the addition of V2O5, MoO3, or WO3 reinforced the glass network cohesion to increase the Tg of the glass. The addition of MoO3or WO3 in the silver tellurite glass increased Tg and crystallization temperature (Tc) with remaining the glass stability.

Silver tellurite glasses with melting temperature of approximately 700°C were developed to immobilize 129I wastes. Longterm dissolution tests in 0.1 M acetic acid and disposability assessment were conducted to evaluate sustainability of the glasses. Leaching rate of Te, Bi and I from the glasses decreased for up to 16 d, then remained stable afterwards. On the contrary, tens to tens of thousands of times more of Ag was leached in comparison to the other elements; additionally, Ag leached continuously for all 128 d of the test owing to the exchange of Ag+ and H+ ions between the glasses and solution. The I leached much lower than those of other elements even though it leached ~10 times more in 0.1 M acetic acid than in deionized water. Some TeO4 units in the glass network were transformed to TeO3 by ion exchange and hydrolysis. These silver tellurite glasses met all waste acceptance criteria for disposal in Korea.

고용량 131I 치료는 분화갑상선암으로 인한 갑상선전절제술을 받은 환자에게 보편적으로 시행되어 왔다. 고용량 131I 치료를 하는 경우 환자로부터 일반인이 받게 되는 피폭선량을 선량한도 이내로 제한하기 위해 환자를 일정 기간 동안 격리하여야 한다. 유효반감기는 환자로부터 가족들이 얼마나 피폭되는지 계산하거 나 격리기간을 결정하는데 중요한 값이다. 이에 본 연구에서는 NM670 SPECT/CT를 이용해 고용량 131I 치 료환자의 유효붕괴상수, 유효반감기, 격리기간을 도출하였다. 본 연구를 통해 고용량 131I 치료환자의 유효반감기를 도출하였고, 체내에 잔류 방사능량이 퇴원기준인 1. 2 GBq 에 도달하는 시간을 확인하였다. 또한 치료선량별 유효반감기를 비교하였을 때 유의한 차이가 없 었으나, 격리기간은 치료선량이 커질수록 격리기간이 길어지는 것을 확인할 수 있었다. 전처치 유형별 유 효반감기를 비교하였을 때 rhTSH 환자군과 THW 환자군의 유효반감기가 유의한 차이를 보이지 않았으나, 격리기간은 rhTSH 환자군이 THW 환자군 보다 짧게 나타났다. 이는 치료선량의 차이로 인해 격리기간이 짧아진 것으로 판단된다. 따라서 현행 의료보험체계(rhTSH 사용 시 3.7 GBq 이하에서 보험적용)가 유지된다면, 전처치 유형별로 구분하여 현행 격리기간(2박 3일)보다 더 이른 시간에 환자를 퇴원시킬 수 있을 것이다.

This research was performed by means of several different virgin granular activated carbons (GAC) made of each coal, coconut and wood, and the GACs were investigated for an adsorption performance of iodine-131 in a continuous adsorption column. Breakthrough behavior was investigated that the breakthrough points of the virgin two coals-, coconut- and wood-based GACs were observed as bed volume (BV) 7080, BV 5640, BV 5064 and BV 3192, respectively. The experimental results of adsorption capacity (X/M) for iodine-127 showed that two coal- based GACs were highest (208.6 and 139.1 μg/g), the coconut-based GAC was intermediate (86.5 μg/g) and the wood-based GAC was lowest (54.5 μg/g). The X/M of the coal-based GACs was 2∼4 times higher than the X/M of the coconut-based and wood-based GACs.

방사성옥소를 이용한 갑상선 암의 치료는 지난 수 십년 동안 사용되어 왔으며 많은 치료효과를 보이면서 앞으로 지속적으로 사용되어 질 전망이고 현재 우리나라의 옥소치료병실 수는 2010년 기준 124개의 치료병실이 운영되고 있으나 아직도 부족한 실정이다. 그래서 많은 병원들이 치료병실을 개설하고 있으나 중요한건 치료병실의 수적 증가보단현재 치료병실의 올바른 관리가 선행되어야 한다는 것이다. 따라서 병실증설에 대한 논의에 앞서 현재 적용되고 있는치료병실의 안전관리 기준과 일부 대학병원에서 기준으로 삼고 있는 안전관리기준을 조사하여 얼마나 잘 지켜지고 있는지, 치료병실의 이용에 따른 전반적인 안전관리실태여부를 조사하여 고찰 하였다.