• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2019년도 춘계학술논문요약집
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• pp.409-410
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• 2019

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 춘계학술논문요약집
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• pp.39-40
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• 2018

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
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• pp.150-164
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• 2004

According to the Korean long-term plan for nuclear technology development, KAERI is conducting a few R&D projects related to the proliferation-resistant back-end fuel cycle. The R&D activities for the back-end fuel cycle are reviewed in this work, especially focusing on the study of the partitioning and transmutation(P&T) of long-lived radionuclides. The P&T study is currently being carried out in order to develop key technologies in the areas of partitioning and transmutation. The partitioning study is based on the development of pyroprocessing such as electrorefining and electrowinning because they can be adopted as proliferation-resistant technologies in the fuel cycle. In this study, various behaviors of the electrodeposition of uranium and rare earth elements in the LiCl-KCl electrorefining system have been examined through fundamental experimental work. As for the transmutation system, KAERI is studying the HYPER (HYbrid Power Extraction Reactor), a kind of subcritical reactor which will be connected with a proton accelerator. Up to now, a conceptual study has been carried out for the major elemental systems of the subcritical reactor such as core, transuranic fuel, long-lived fission product target, and the Pb-Bi cooling system, etc. In order to enhance the transmutation efficiency of the transuranic elements as well as to strengthen the reactor safety, the reactor core was optimized by determining its most suitable subcriticality, the ratio of height/diameter, and by introducing the concepts of optimum core configuration with a transuranic enrichment as well as a scattered reloading of the fuel assemblies.

• 자원리싸이클링
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• 제24권3호
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• pp.11-15
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• 2015

주석을 함유한 폐기물에서 고순도 주석을 회수하는 기술을 개발하기 위해 주석오니의 환원 제련 및 전해정련에 대해 연구하였다. 2단계의 건식제련을 통해 주석오니에 함유된 주석산화물을 환원시켜 92.7%의 주석을 회수하였다. 또한 건식공정으로 회수한 조주석을 전해정련시켜 순도를 99.87%까지 증가시켰다. 본 연구결과는 국내에서 발생하는 폐자원으로부터 주석을 회수하여 국내 주석 소비량의 일부를 대체할 수 있는 상용화기술의 토대가 될 수 있다.

• Nuclear Engineering and Technology
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• 제44권7호
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• pp.767-772
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• 2012

In support of optimizing electrorefining technology for treating spent nuclear fuel, lithium drawdown has been investigated for separating actinides from molten salt electrolyte. Drawdown reaction selectivity is a major issue that requires investigation, since the goal is to remove actinides while leaving the fission products and other components in the salt. A series of lithium drawdown tests with surrogate fission product chlorides was run to obtain selectivity data with non-radioactive salts, develop a predictive model, and draw conclusions about the viability of using this process with actinide-loaded salt. Results of tests with CsCl, $LaCl_3$, $CeCl_3$, and $NdCl_3$ are reported here. Equilibrium was typically achieved in less than 10 hours of contact between lithium metal and molten salt under well-stirred conditions. Maintaining low oxygen and water impurity concentrations (<10 ppm) in the atmosphere was observed to be critical to minimize side reactions and maintain stable salt compositions. An equilibrium model has been formulated and fit to the experimental data. Good fits to the data were achieved. Based on analysis and results obtained to date, it is concluded that clean separation between minor actinides and lanthanides will be difficult to achieve using lithium drawdown.

• 자원리싸이클링
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• 제24권2호
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• pp.23-28
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• 2015

현재 국내에서 소비되는 주석의 대부분은 수입에 의존하고 있다. 본 연구에서는 평판 유리, LCD 패널 유리 기판 생산시 발생하는 주석 용탕에 함유된 주석산화물을 건식법으로 회수하는 공정을 조사하였다. 환원반응온도를 변화시키며 주석의 회수율을 조사한 결과 $1350^{\circ}C$에서 최대 회수율을 얻을 수 있었다. 또한 주석 산화물의 1차 제련과 슬래그의 2차 제련을 통해 88%의 회수율을 얻었다. 건식공정으로 회수된 조주석을 전해정련처리하여 99.9%의 순도를 지닌 주석 금속을 제조하였다.

• Nuclear Engineering and Technology
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• 제40권3호
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• pp.183-190
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• 2008

Pyroprocessing is the optimal means of treating spent metal fuels from metal fast fuel reactors and is proposed as a potential option for GNEP in order to meet the requirements of the next generation fuel cycle. Currently, efforts for research and development are being made not only in the U.S., but also in Asian countries. Electrorefining, cathode processing by distillation, injection casting for fuel fabrication, and waste treatment must be verified by the use of genuine materials, and the engineering scale model of each device must be developed for commercial deployment. Pyroprocessing can be effectively extended to treat oxide fuels by applying an electrochemical reduction, for which various kinds of oxides are examined. A typical morphology change was observed following the electrochemical reduction, while the product composition was estimated through the process flow diagram. The products include much stronger radiation emitter than pure typical LWR Pu or weapon-grade Pu. Nevertheless, institutional measures are unavoidable to ensure proliferation-proof plant operations. The safeguard concept of a pyroprocessing plant was compared with that of a PUREX plant. The pyroprocessing is better adapted for a collocation system positioned with some reactors and a single processing facility rather than for a centralized reprocessing unit with a large scale throughput.

• Nuclear Engineering and Technology
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• 제47권7호
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• pp.849-858
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• 2015

This study set the pyroprocess facility at an engineering scale as a cost object, and presented the cost consumed during the unit processes of the pyroprocess. For the cost calculation, the activity based costing (ABC) method was used instead of the engineering cost estimation method, which calculates the cost based on the conceptual design of the pyroprocess facility. The calculation results demonstrate that the pyroprocess facility's unit process cost is $194/kgHM for pretreatment, $298/kgHM for electrochemical reduction, $226/kgHM for electrorefining, and $299/kgHM for electrowinning. An analysis demonstrated that the share of each unit process cost among the total pyroprocess cost is as follows: 19% for pretreatment, 29% for electrochemical reduction, 22% for electrorefining, and 30% for electrowinning. The total unit cost of the pyroprocess was calculated at $1,017/kgHM. In the end, electrochemical reduction and the electrowinning process took up most of the cost, and the individual costs for these two processes was found to be similar. This is because significant raw material cost is required for the electrochemical reduction process, which uses platinum as an anode electrode. In addition, significant raw material costs are required, such as for $Li_3PO_4$, which is used a lot during the salt purification process.

• 방사성폐기물학회지
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• 제15권4호
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• pp.321-332
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• 2017

전극 구성에 따른 고효율 전해정련공정의 일반적인 모델을 구축하기 위하여, 상미분방정식 인터페이스를 갖는 COMSOL Multiphysics V5.3 전착 모듈을 사용하여 수치해석을 실시하였다. 구축된 모델은 한국원자력연구원에서 제작한 실험실 규모 (1kg 우라늄/day 규모) 다중배열전극 전해정련장치를 사용해 전극 간 거리, 전극 배열을 변수로 하여 실시한 실험의 전류밀도-전위 곡선과 비교하였다. 공정온도는 $500^{\circ}C$이다. 용융염은 3wt% $UCl_3$가 포함된 LiCl-KCl 공융염을 사용하였다. 검증된 모델을 이용하여 전류밀도-셀전위 곡선을 계산한 결과 전극 간 거리가 가까울수록, 전극 배열은 양극/음극 면적비가 증가할수록 셀 전위가 낮아져 전해정련장치의 우라늄 처리효율을 향상시킬 수 있다는 것을 확인하였다. 이러한 접근은 고출력 사용후핵연료 전해정련기의 안전설계를 위한 데이터베이스 구축에 유용할 것이다.

• 방사성폐기물학회지
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• 제13권4호
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• pp.263-269
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• 2015

산화물 사용후핵연료에 대한 전해환원의 금속전환체를 양극으로 한 전해정련공정에는 LiCl-KCl 공융염에 우라늄 원소뿐 아니라 초우란 원소 및 희토류 원소들이 용해되므로 우라늄을 선택적으로 회수하기 위해서는 우라늄과 다른 원소들이 음극에 전착되는 거동에 대한 연구가 필요하다. LiCl-KCl 공융염 내 희토류 원소의 농도에 따른 음극에서의 전착거동을 고찰하기 위해 U 및 Ce를 기준으로 한 U, Ce, Y 그리고 Nd 원소들의 분리계수에 대한 연구를 수행하였다. Ce 금속을 희생 양극으로 이용하여 정전류 정련반응을 통해 용융염 상과 전착물 상의 U, Ce, Y 그리고 Nd 원소의 농도를 분석하여 이로부터 분리계수를 얻었으며 $UCl_3$ 농도와 $CeCl_3/UCl_3$ 농도비에 따른 분리계수로부터 우라늄을 선택적으로 회수할 수 있는 조건들을 고찰하였다.