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오맹교,이근영,( Richard Ian Foster ),김광욱,이창하 한국공업화학회 2020 한국공업화학회 연구논문 초록집 Vol.2020 No.-
Concrete building materials are one of the major radioactive wastes generated during the decommissioning of nuclear facilities. Mechanical and chemical treatment processes are available to separate the radioactive materials from the concrete. However these processes generate a large volume of secondary radioactive wastewater. In this research, we aim to remove the simulate radioactive nuclides using precipitation. The experiments were carried out using a simulated wastewater, formed by the dissolution of concrete within HCl, to which non-radioactive Cs, Sr, Co and Eu were added. Characteristics of precipitation were affected by the variation of pH and the injection of complexation agents. If it is treated effectively, this approach can be applied to the treatment of radioactive wastewater to satisfy the discharge criteria.
이근영,오맹교,김지민,이일희,김익수,김광욱,정동용,서범경,Lee, Keun-Young,Oh, Maengkyo,Kim, Jimin,Lee, Eil-Hee,Kim, Ik-Soo,Kim, Kwang-Wook,Chung, Dong-Yong,Seo, Bum-Kyoung 한국방사성폐기물학회 2018 방사성폐기물학회지 Vol.16 No.1
In Korea, a huge amount of radioactive concrete waste will be generated through decommissioning of nuclear facilities in the near future; therefore, optimum technology for the treatment of concrete waste should be reviewed thoroughly and the future direction of technology development should be discussed. In this paper, many domestic and foreign examples of generation of radioactive concrete waste were pieced together and the characteristics of radioactive concrete waste were examined. Moreover, we reviewed trends in technology development by analyzing the examples of various studies and practical applications of treatment technologies, such as mechanical decontamination, chemical decontamination, volume reduction, recycling and solidification, and also tried to understand the limitations of existing technologies and determine a direction for technical improvement.
방사화 콘크리트 분말의 용해액으로부터 용매추출에 의한 코발트와 유로퓸의 분리
김익수,오맹교,이근영 한국공업화학회 2019 한국공업화학회 연구논문 초록집 Vol.2019 No.0
원자력 시설의 해체 시 발생하는 막대한 양의 콘크리트 폐기물을 줄이기 위한 감용 기술 개발의 일환으로 방사화 콘크리트 분말의 용해액으로부터 방사성 핵종을 분리 제거하기 위한 공정을 개발하고자 한다. 이를 위한 기초 연구로서 코발트와 유로퓸이 함유된 콘크리트 분말의 염산 용해액으로부터 두 핵종을 분리하기 위한 용매추출 실험을 수행하였다. 추출제로는 D2EHPA를 사용하였고 유기상 용매로는 n-Dodecane을 사용하였으며, 코발트와 유로퓸을 효율적으로 분리 제거하기 위하여 추출제의 농도 및 수용액의 pH 등을 변화시켜가며 추출 조건에 따른 추출 거동을 조사하였다. 추출제의 농도가 높을수록 그리고 O/A ratio가 클수록 추출률은 증가하였다. 유로퓸은 초기 염산 용액의 pH가 2 이하일 때 99% 이상 추출되었으며, 코발트는 pH가 3 이상일 때 95%까지 추출되었다. 용액의 pH를 다르게 조절하는 다단계 추출공정에 의해 유로퓸과 코발트를 콘크리트 용해액으로부터 모두 분리 제거할 수 있음을 확인하였다.
Chlorination behavior of Li(Ni1/3Co1/3Mn1/3)O2
전민구,김성욱,오맹교,은희철,이근경 한국화학공학회 2022 Korean Journal of Chemical Engineering Vol.39 No.9
The chlorination behavior of Li(Ni1/3Co1/3Mn1/3)O2 (NCM) was investigated as a function of the reaction temperature(400-600 oC) and time (1-8 h) for application in a chlorination-based recycling process. Structural analysis resultsrevealed that chlorination leads to a sequential transition from a hexagonal LiMO2 structure to a hexagonal Li1x'MO2y'(observed only at 400 oC), a hexagonal Li1xMO2y (xx', yy', at 400-600 oC), and a spinel-type M3O4 phase (500 oC,M represents Ni,Co,Mn). It was also found that this structural transition is accelerated by an increase in the reactiontemperature, except at 600 oC, where the thermal decomposition of the Li1xMO2y phase inhibited the formation of theM3O4 phase. Weight changes of the samples suggested that the chlorination of the transition metals begins at 500 oCand that its rate increases with an increase in the reaction temperature. It was revealed by a composition analysis thatan increase in the reaction temperature (except at 600 oC) and longer times result in a higher Li removal ratio. A temperatureof 550 oC was proposed as the optimum temperature for the chlorination of NCM in consideration of thefindings from this work.