• Proceedings of the Korean Radioactive Waste Society Conference
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• 2011.05a
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• pp.165-166
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• 2011

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2010.05a
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• pp.225-226
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• 2010

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2007.05a
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• pp.158-159
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• 2007

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.06a
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• pp.307-308
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• 2009

증류공정 개발을 위한 자료를 얻기 위하여, 카드뮴 증류장치를 제작하고 여러 조건에서 카드뮴의 증류속도를 측정하였으며, 액체음극으로부터 악티나이드 원소 회수 연구에 필요한 금속간 화합물을 전해방법에 의해 성공적으로 제조하였다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2006.06a
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• pp.97-98
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• 2006

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.3 no.3
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• pp.193-200
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• 2005

[ $^{14}C$ ] and $^{3}H$ in the evaporator bottom (EB) discharged from the Nuclear power plant (NPP) were extracted simultaneously into a gaseous $^{14}CO_{2}$ and liquefied HTO by using the chemical oxidation, which is the method to oxidize samples completely using potassium persulfate and sulfuric acid. The extracted $^{14}C$ and $^{3}H$ were counted by the liquid scintillation counter (LSC) after the quench correction. To examine the recovery of $^{14}C$ using the radioactive standards, $Na_{2}^{14}CO_{3}$, $^{14}C-alcohol$, and $^{14}C-toluene$ as $^{14}C$, and HTO as $^{3}H$ were used. Also, the most suitable method for oxidizing $^{14}C-toluene$, which is difficult to be oxidized, was investigated through FT-IR spectra according to the concentration of sulfuric acid. With the identical method, $^{14}C$ and $^{3}H$ in the EB generated in the NPP were assayed in the range of $8.35{\sim}l.38{\times}10^3$ Bq/g and $2.46{\times}10^2{\sim}1.40{\times}10^4$ Bq/g, respectively.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.54-59
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• 2003

Several radionuclides are considered as an object of the assesment to develop a scaling factor and a periodical verification method which are needed for the evaluation of radionuclide inventory of various radioactive wastes from nuclear power plants in Korea. A selective separation of $^{55}Fe$, $^{90}FSr$ 및 $^{94}Nb$ which should be recovered individually for the radiochemical analysis was described in detail. Sorption and desorption behaviours of ion exchange and extraction chromatographic resins for Fe, Sr, Nb and co-existing metal ions were Investigated using an artificial waste solution simulated of chemical composition of real radioactive wastes. Separation conditions available for the sequential recovery of these metal ions from a single sample were optimized to minimize a discharge of radioactive wastes produced through the analytical process and a radiation exposure to analysts. Their recovery yields were measured with reliability.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2007.05a
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• pp.65-66
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• 2007

원자력 발전소 방사선 관리구역 1차 계통수의 수질 정화 후 발생된 고선량 폐필터를 방사능 붕괴 후 잡고체 폐기물로 처리하기 위한 장기저장시설 내 설치 될 설비 임. 동 설비는 자동화공정을 기본으로 한정된 공간에 다량의 폐필터를 가장 효율적으로 저장 할 수 있는 최적의 설비이며, 폐필터 장입, 인출 시 작업시간단축, 작업자 피폭저감, 오염확산 방지는 물론 폐기물을 감용시켜 폐기물처리, 처분 비용 절감에 기여하고자 한다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.06a
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• pp.196-199
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• 2005

The centrifuge system in liquid radwaste system(LRS) is composed of several skids including Decanter and Separator. The decanter separates the sludge over 5mm in size within liquid radwaste by centrifuge force and drops it into 55gallon drum. The separator separates the sludge over $0.1{\mu}m$ in size within the liquid radwaste processed by Decanter by centrifuge force. The process of separating the sludge from the LRS keeps the resin in Ion Exchanger from being damaged and improves the performance of Ion Exchanger, and satisfies the decontamination factor suggested in Uljin 5,6 FSAR to safety discharge into the outer environment.

• Nuclear industry
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• v.18 no.7 s.185
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• pp.64-69
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• 1998