During decommissioning and site remediation of nuclear power plant, large amount of wastes (including radioactive waste) with various type will be generated within very short time. Among those wastes, soil and concrete wastes is known to account for more than 70% of total waste generated. So, efficient management of these wastes is very essential for effective NPP decommissioning. Recently, BNS (Best System) developed a system for evaluation and classification of soil and concrete wastes from the generation. The system is composed of various modules for container loading, weight measurement, contamination evaluation, waste classification, stacking, storage and control. By adopting modular type, the system is good for dealing with variable situation where system capacity needs to be expanded or contracted depending on the decommissioning schedule, good for minimizing secondary waste generated during maintenance of failed part and also good for disassemble, transfer and assemble. The contamination evaluation module of the system has two sub module. One is for quick measurement with NaI(Tl) detector and the other is for accurate measurement with HPGe detector. For waste transfer, the system adopts LTS (Linear Transfer System) conveyor system showing low vibration and noise during operation. This will be helpful for minimizing scattering of dust from the waste container. And for real time positioning of waste container, wireless tag was adopted. The tag also used for information management of waste history from the generation. Once a container with about 100 kg of soil or concrete is loaded, it is moved to the weight measurement module and then it transfers to quick measurement module. When measured value for radioactivity concentration of Co- 60 and Cs-137 is more than 1.0 Bq/g, then the container is classified as waste for disposal and directly transferred to stacking and storage rack. Otherwise, the container is transferred to accurate measurement module. At the accurate module, the container is classified as waste for disposal or waste for regulatory clearance depending on the measurement result of 0.1 Bq/g. As the storage rack has a sections for disposal and regulatory clearance respectively, the classified containers will be positioned at one of the sections depending on the results from the contamination evaluation module. The system can control the movement of lots of container at the same time. So, the system will be helpful for the effective nuclear power plant decommissioning in view of time and budget.

In the case of decommissioning of a nuclear power plant, it is expected that a significant amount of VLLW and LLW that need to be disposed of are also expected. Conventional reduction technology is a method of extracting or removing radionuclides from waste, but this project is being carried out for the purpose of obtaining a reduction effect through the development of a material that treats another radioactive waste using radioactive waste. In this paper, the technology of impregnating LiOH capable of adsorbing radiocarbon to the gas filter material manufactured from concrete and soil waste as raw materials and the radiocarbon removal performance were reviewed. In this study, a raw material of ceramic filter was prepared by mixing concrete and soil waste with a powder of 40 m or less, and after sintering at 1,250°C, 5wt% to 40wt% of LiOH is impregnated with a filter capable of adsorbing carbon dioxide. was prepared. The prepared filter used ICP-OES and XRD to confirm the LiOH deposition result, and the concentration of carbon dioxide discharged through the carbon dioxide adsorption device was confirmed. It was possible to obtain the result that the amount of adsorption was changed depending on the flow rate of carbon dioxide supplied and the amount of material. Through this, it was possible to confirm the possibility of power generation in the adsorption performance of gas. In this study, after crushing waste concrete and waste soil, powders of 40 m or less were mixed with other additives to prepare raw materials for ceramic filters, and sintered at 1,250°C to manufacture filters. 5wt% to 40wt% of LiOH was impregnated on the prepared filter to give functionality to enable carbon dioxide adsorption. The results of LiOH deposition were confirmed using ICP-OES and XRD, and the change in the concentration of carbon dioxide emitted through a separately prepared adsorption device was confirmed. It was possible to obtain the result that the amount of adsorption was changed according to the flow rate of carbon dioxide supplied and the amount of material, and the possibility of developing a material for radioactive waste treatment using radioactive waste was confirmed when the porosity and specific surface area of the filter material were increased.

As the design life of nuclear power plants are coming to the end, starting with Kori unit 1, nuclear power related organizations have been actively conducted research on the treatment of nuclear power plant decommissioning waste. In this study, among various types of radioactive waste, stabilization and volume reduction experiments were conducted on radioactive contaminated soil waste. Korea has no experience in decommissioning nuclear power plants, but a large amount of radioactively contaminated soil waste was generated during the decommissioning of the KAERI research reactor (TRIGA Mark- II) and the uranium conversion facility. This case shows the possibility of generating radioactive soil waste from nuclear power plants and nuclear-related facilities sites. Soil waste should be solidified, because its fluidity and dispersibility wastes specified in the notification of the Korea Nuclear Safety and Security Commission. In addition, the solidified waste forms should have sufficient mechanical strength and water resistance. Numerous minerals in the soil are components that can make glass and ceramics, for this reason, glass-ceramic sintered body can be made by appropriate heat and pressure. The sintering conditions of soil were optimized, in order to make better economical and more stable sintered body, some additives (such as additives for glass were mixed) with the soil and sintering experiments were conducted. Uncontaminated natural soil was collected and used for the experiment after air drying. Moisture content, pH, bulk density, and organic content were measured to understand the basic properties of soil, and physicochemical properties of the soil were identified by XRD, XRF, TG, and SEM-EDS analysis. In order to understand the distribution by particle size of the soil, it was divided into Sand (0.05–2 mm) and Fines (< 0.05 mm). The green body was manufactured in the form of a cylinder with a diameter of 13mm and a height of about 10mm. Appropriate pressure (> 150 MPa) was applied to the soil to make a green body, and appropriate heat (> 800°C) was applied to the sintered body to make a sintered body. The sintering was conducted in a muffle furnace in air conditions. The volume reduction and compressive strength of the sintered body for each condition were evaluated.

경주 방사성 폐기물 처분장 주변 논에 대한 방사성 요오드 및 테크네튬의 토양-쌀알 전이계수를 조사하 기 위하여 온실 내에서 포트재배로 방사성 추적자 실험을 2 년에 걸쳐 수행하였다. 모내기 전에 상부 약 20 cm 깊이의 흙을 125I(2007 년) 및 99Tc(2008 년)와 고르게 혼합한 다음 포트에 관개하여 물이 찬 논같 이 만들었다. 전이계수는 토양 중 방사성 핵종 농도에 대한 쌀알(현미) 내 농도의 비로 나타내었다. 쌀알 의 방사성 요오드 및 테크네튬 전이계수는 토양에 따라 각각 1.1×10-3∼6.4×10-3(세 토양) 및 5.4×10-4∼2.5×10-3(네 토양)의 범위였다. 이러한 변이에 대해서는 토양 간 점토 함량의 차이가 유기물 함량이나 pH의 차이보다 중요한 역할을 한 것으로 보였다. 쌀알의 방사성 요오드 및 테크네튬 전이계수의 대표치 로서 각각 2.9×10-3 및 1.1×10-3이 제안되었다. 앞으로 보다 대표성이 높은 값을 얻기 위하여 관심 부지 들을 대상으로 조사가 지속적으로 수행될 필요가 있다.

방사성 토양을 복원하기 위해 원자력시설 주변 부지의 수리지질 특성을 분석하여 국내 방사성 토양 복원에 적합한 수직형 동전기세정장치를 개발하였다. 또한, 이 수직형 동전기세정장치를 이용한 실험을 통해 원자력시설 주변 방사성토양을 복원하기 위한 최적 세정제를 선정하고 단기간에 높은 제거효율을 확보할 수 있는 최적제염조건들을 도출하였다. 초산을 세정제로 사용하였을 때 토양으로부터 코발트와 세슘의 제거효율이 가장 높으므로 동전기제염을 위한 최적 세정제로 초산을 선정하였다. 동전기세정제염 시 세정제 주입량을 증가 시켰을 때 토양으로부터 코발트와 세슘의 제거효율은 평균 약 4.6% 제거효율이 증가했고 토양폐액 발생량도 동전기제염의 1.5배인 2.4 mL/g이었다. 동전기토양셀의 전압구배를 2배로 증가시켜 4 V/cm를 적용시켰을 때, 코발트와 세슘의 제거효율은 각각 98.9%와 96.7%로 평균 약 4.3% 제거효율이 증가했다. 그리고 세정제 농도를 0.01M로부터 0.05M로 증가시킨 후 제염실험 결과 코발트의 제거효율은 상승했지만 세슘의 제거효율은 감소하였다. 위 실험결과 개발한 수직형 동전기세정장치의 최적제염조건으로 제염시간은 20일 동안 초산 0.01M∼0.05M을 세정제로 사용하여 동전기토양셀의 전압구배는 4 V/cm를 가하고, 2.4 mL/g의 세정제를 주입하는 것이다.

방사성물질의 대기 누출 사고시 환경에서 핵종 거동을 모사하는 동적 섭식경로모델 DYNACON을 개선하여, 가축 (육우)의 공기 흡입과 토양 섭취가 육류 (쇠고기)의 방사능 오염에 미치는 영향을 고찰하였다. 이들 두 오염경로는 누출이 육우의 비방목 기간에 일어나는 경우에 육류의 오염에 있어서 결코 무시될 수 없는 경로라는 사실을 확인하였다. 특히 누출 후 대부분 기간에 걸쳐 토양 섭취에 의한 육류의 오염 영향이 공기 흡입에 의한 영향에 비해 우세하였다. 누출 기간동안 강우는 토양 섭취에 의한 육류의 오염에 중요한 요소로 작용하였으며, 이러한 현상은 단반감기 핵종인 보다 장반감기 핵종인 의 경우에 보다 뚜렷하였다. 이전에 수행된 우유에 대한 분석 결과와 비교하여 공기 흡입과 토양 섭취는 육류에 대해 보다 중요한 오염경로로 나타났는데, 이는 상대적으로 육류에서 핵종의 긴 생물학적 반감기 때문이다. 방목기간에 방사성물질이 대기로 누출되는 경우 누출 기간동안 강우의 유무에 관계없이 목초 섭취에 의한 오염 영향이 지배적이었으며, 결과적으로 토양 섭취와 공기 흡입에 의한 오염 영향은 우유의 경우와 마찬가지로 무시할 수 있는 수준이었다.

About 4,800 soil drums were generated in the process of maintenance on KRR site (Korea Research Reactor) in Seoul. Most of the drums are processed by regulatory clearance in 2007-2008 and the remaining 1800 drums are currently stored in KAERI (Korea Atomic Energy Research Institute). To decide a treatment method of radioactive soil for final disposal, the soil is classified according to a particle size. Based on the results of the radioactivity concentration for the classified soil, methods such as regulatory clearance, decommissioning, and solidification were decided. Many papers show that radioactive soil is disposed of using a decontamination agent or other method. But it is difficult to decontaminate radioactive particles from fine soil particles because the adsorptive power of fine soil particles is too strong. This study was focused on finding a particle size distribution of radioactive soil that can be used as an operating range for cement solidification produced by a suitable ratio of radioactive soil for final disposal. Workability, free-standing water, compressive strength, immersion, and leaching tests were carried out to evaluate characteristics of the cement solidification. Cement solidification is the only method for final disposal because radioactive soil particle sizes below 500 μm exceed the regulatory clearance criteria (< 0.1 Bq/g). According to the test results for cement solidification, 0.4 water/cement and 0.5 soil/cement ratios are the most appropriate operating ranges.