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Characteristics of Vitrification Process and Vitrified Form for Radioactive Waste
Cheon-Woo Kim,Ji-Yean Kim,Jong-Rak Choi,Pyung-Kook Ji,Jong-Kil Park,Sang-Woon Shin,Jong-Hyun Ha,Myung-Jae Song 한국방사성폐기물학회 2004 방사성폐기물학회지 Vol.2 No.3
In order to vitrify the combustible dry active waste (DAW) generated from Korean Nuclear Power Plants, a glass formulation development based on waste composition was performed. A borosilicate glass, DG-2, was formulated to vitrify the DAW in an induction cold crucible melter (CCM). The processability, product performance, and volume reduction effect of the candidate glass were evaluated using a computer code and were measured experimentally in the laboratory and CCM. The glass viscosity and electrical conductivity as the process parameters were in the desired ranges. Start-up and maintaining glass melt of the candidate glass were favorable in the CCM. The product of the glass product such as chemical durability, phase stability, and density was satisfactory. The vitrification process using the candidate glass was also evaluated assuming that it was operated as economically as possible.
Characteristics of Vitrification Process and Vitrified Form for Radioactive Waste
Kim, Cheon-Woo,Kim, Ji-Yean,ChoI, Jong-Rak,Ji, Pyung-Kook,Park, Jong-Kil,Shin, Sang-Woon,Ha, Jong-Hyun,Song, Myung-Jae Korean Radioactive Waste Society 2004 방사성폐기물학회지 Vol.2 No.3
In order to vitrify the combustible dry active waste (DAW) generated from Korean Nuclear Power Plants, a glass formulation development based on waste composition was performed. A borosilicate glass, DG-2, was formulated to vitrify the DAW in an induction cold crucible melter (CCM). The processability, product performance, and volume reduction effect of the candidate glass were evaluated using a computer code and were measured experimentally in the laboratory and CCM. The glass viscosity and electrical conductivity as the process parameters were in the desired ranges. Start-up and maintaining glass melt of the candidate glass were favorable in the CCM. The product of the glass product such as chemical durability, phase stability, and density was satisfactory. The vitrification process using the candidate glass was also evaluated assuming that it was operated as economically as possible.
Chon,Je-Keun,Kim,Byung-Tae,Ji,Pyung-Kook,Kwak,Sang-Soo,Park,Chong-Mook 대한방사선 방어학회 1998 방사선방어학회지 Vol.23 No.1
몇 종류의 제염제에 대한 제염효과를 평가하기 위해 CO과 Cs에 대한 의한 피부오염의 제염실험을 수행하였다. 본 연구에서는 인체피부 대신에 돼지피부를 활용하였으며, 피부오염용액으로는 CoCl₂와 CsCl 용액을 사용하였다. 그리고 제염제로는 현재 사용되고 있는 비눗물, EDTA 외에 오염된 구조물의 표면오염 제거를 위해 원자력 연구소에서 개발한 KAERICON과 본 연구를 통해 제조한 IOCON, TRICON 및 CHARCON 등을 이용하여 피부오염에 대한 제염을 실시하여 각 제염제의 제염효과를 평가하였다. 방사성물질의 피부침투정도를 파악하기 위하여 16시간동안 방사성물질을 시료표면에 점착시킨후 감사선 측정을 통해 침투율을 평가하였으며, 이 실험에서 Cs의 경우 11.5% Co의 경우 3.2% 정도가 피부로 침투됨을 알 수 있다. 각 제염제의 제염효과를 평가해본 결과 KAERICON은 Cs에 대하여 최고 52.1%(제염계수 2.1)의 제염율을 나타내었으며, IOCON도 Cs에 대하여 비교적 좋은 제염율(제염계수 1.9)을 나타내었다. 그러나 Co에 대해서는 I|OCON, CHARCON 모두 20%(제염계수 1.2)미만의 제염율을 나타내었으며 KAERICON도 Co에 대해 낮은 제염율(제염계수 1.1)을 나타내었다. TRICON은 Cs에 대해 1.6~1.8의 제염계수를 나타내었으며, Co에 대해서는 1.0~1.2의 제염계수를 나타내었다. In order to evaluate the effectiveness of some decontamination agents against skin contamination of Co and Cs, the experiments were carried out in this study. In the experiments, pig skin was used instead of human skin, 60CoCl₂and 137CsCl were used the liquid sources of skin contamination. To examine the effectiveness of decontamination agents, skin decontamination was tried using soup, EDTA, KAERICON which was developed for decontamination of radionulides on the surface of building structure, are new decontamination agents such as IOCON, TRICON, and CHARCON, which were developed in this study. The absorption of radionuclides through the skin was evaluated by the gamma-ray detection on the surface of sample skin after radionuclides were penetrated into the skin during 16 hour soiling time. The results of this absorption experiment indicated that 11.5% and 3.2% of initial amounts of 137Cs and 60Co, respectively, were panerated into the skin. In the experiment to remove the residual radioactivity fixed on the skin, KAERICON showed the decontamination rates up to 52.1%(decontamination factor of 2.1) and IOCON showed the equivalent decontamination rate (decontamination factor 1.9) for Cs. however, IOCON and CHARCON showed the poor decontamination rates of less than 20%(decontamination factor of 1.2)for Co, and KAERICON showed the poor decontamination rate (decontamination factor 1.1) for Co. For TRICON, the decontamination factors were 1.6 to 1.8 for Cs, and 1.0 to 1.2 for Co, repectively.
Jeong-JIn Lee,Hyung-Yeal Pyo,Jong-Seon Jeon,Chang Heon Lee,Kwang-Yong Jee,Pyung-Kook Ji 한국방사성폐기물학회 2004 방사성폐기물학회지 Vol.2 No.4
원자력 발전소에서 발생하는 고체 방사성 폐기물인 이온교환수지, 제올라이트, 활성탄 및 슬러지 에 포함된 성분 원소 분석을 위한 산분해 조건을 확립하였다. 방사성 폐기물의 분해 에는 흔합산을 이용한 밀폐형 극초단파 산분해법을 사용하였으며, 제안한 방법에 따른 산분해 후의 용액은 맑고 색이 없는 투명한 상태임을 확인할 수 있었다. 또한, 산분해 과정을 거친 각각의 용액 시료는 ICP-AES와 AAS를 사용하여 분석하였고, 모의 방사성 폐기물에 첨가한 5종의 금속 원소들은 이상의 높은 회수율을 보여주었다. 화학적 특성을 고려하여 제안된 산분해 조건에 의해 용액화된 중저준위 방사성 폐기물의 성분 원소 분석은 최적의 유리화 기술 개발을 위한 기초 자료로 유용하게 사용될 수 있을 것으로 판단된다. The conditions are obtained for the decomposition of solid radioactive wastes, including ion exchange resin, zeolite, charcoal, and sludge from nuclear power plant. In the process of decomposing the radioactive wastes was used the microwave acid digestion method with mixed acid. The solution after acid digestion by the following method was colorless and transparent. Each solution was analyzed with ICP-AES and AAS and the recovery yield for 5 different elements added into the simulated radioactive wastes were over . The elemental analysis of destructive low and medium level radioactive wastes by the proposed microwave acid digestion conditions concerning the chemical characteristics of each radioactive waste are expected to be useful basic data for development of optimal glass formulation.
밀폐형 극초단파 산분해법을 이용한 중${\cdot}$저준위 방사성폐기물의 성분 원소 분석
이정진,표형열,전종선,이창헌,지광용,지평국,Lee Jeong-Jin,Pyo Hyung-Yeal,Jeon Jong-Seon,Lee Chang-Heon,Jee Kwang-Yong,Ji Pyung-Kook 한국방사성폐기물학회 2004 방사성폐기물학회지 Vol.2 No.4
The conditions are obtained for the decomposition of solid radioactive wastes, including ion exchange resin, zeolite, charcoal, and sludge from nuclear power plant. In the process of decomposing the radioactive wastes was used the microwave acid digestion method with mixed acid. The solution after acid digestion by the following method was colorless and transparent. Each solution was analyzed with ICP-AES and AAS and the recovery yield for 5 different elements added into the simulated radioactive wastes were over $94{\%}$. The elemental analysis of destructive low and medium level radioactive wastes by the proposed microwave acid digestion conditions concerning the chemical characteristics of each radioactive waste are expected to be useful basic data for development of optimal glass formulation.