• 방사성폐기물학회지
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• 제20권1호
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• pp.127-131
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• 2022

The structural safety of prototype transport and storage containers for very low-level radioactive liquid waste was experimentally estimated for its localization development. Transport containers for radioactive liquid waste have been researched and developed, however, there are no standardized commercial containers for very low-level radioactive waste in Korea. In this study, the structural safety of the designated IP-2 type container capable of transporting and temporarily storing large amounts of very low-level liquid waste, which is generated during the operation and decommissioning of nuclear power plants, was demonstrated. The stacking and drop tests, which were conducted to determine the structural integrity of the container, verified that there was no external leakage of the contents in spite of its structural deformation due to the drop impact. This study shows the effort required for the localization of the technology used in manufacturing transport and storage containers for very low-level radioactive liquid waste, and the additional structural reinforcement of the container in which the commercial intermediate bulk container (IBC) external frame was coupled.

• 한국콘크리트학회:학술대회논문집
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• 한국콘크리트학회 1996년도 가을 학술발표회 논문집
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• pp.37-43
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• 1996

The high Temperatures and long residence times in the combustion zones of cement kiln can use to burn liquid and solid wastes, such as fuel-wastes, sludges and tire-wastes. To the lastest time, treatment methods of industrial waste are incineration treatment, ocean dumping and land dumping. These are the main methods, but all of them may cause vatious kinds of secondary pollution, including air pollution and water pollution. From this point of view, to reuse the Reclaiming-Fuel in Cement Kiln is the most outstanding waste treatment plant in the world and dose not cause any pollution at all.

• 청정기술
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• 제24권2호
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• pp.119-126
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• 2018

This study introduced a treatment process that was developed to treat Indonesian low-rank coal with high-ash content, which has the same characteristics as residual coal from the biosolubilization process. The treatment process includes separation of ash, solid-liquid separation, pelletizing, and drying. To reduce the ash content, flotation was performed using 4-methyl-2-pentanol (MIBC) as frother, and kerosene, waste oil, and cashew nut shell liquid (CNSL) as collectors. The increasing amount of collector had an effect on combustible coal recovery and ash reduction. After flotation, a filter press, extruder, and an oven drier were used to make a dried coal pellet. Then another coal pellet was made using asphalt as a binder. The compressive strength and friability of the coal pellets were tested and compared.

• Membrane and Water Treatment
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• 제9권5호
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• pp.327-334
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• 2018

The nano/micro composites with highly porous surface area have attracted of great interest, particularly the synthesis of porous and thin film sheets of high performance. In this paper, an easy method of cost-effective synthesis of thin film ceramic fiber membranes based on Hydroxyapatite, and activated carbon by turned into studied to be applied within the service-facilitated the transport of radioactive waste such as $^{90}Sr$, $^{137}Cs$ and $^{60}Co$) as activated product of radioisotopes from ETRR-2 research reactor and dissolved in 3M $HNO_3$, across a thin flat-sheet supported liquid membrane (TFSSLM). Radionuclides are transported from alkaline pH values. The presence of sodium salts in the aqueous media improves in $HNO_3$, the lowering of permeability because the initial $HNO_3$ concentration is improved. The study some parameters on the thin sheet ceramic supported liquid membrane. EDTA as stripping phase concentration, time of extraction and temperature were studied. The study of maximum permeability of radioisotopes for all parameters. The pertraction of a radioactive waste solution from nitrate medium were examined at the optimized conditions. Under the optimum experimental 98.6-99.9% of $^{90}Sr$, 79.65-80.3% of $^{137}Cs$ and $^{60}Co$ 45.5-55.5% in 90-110 min with were extracted in 10-30 min, respectively. The process of diffusion in liquid membranes is governed by the chemical diffusion process.

• 한국분무공학회지
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• 제18권4호
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• pp.182-187
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• 2013

This study was performed to investigate the effect of biodiesel derived from waste cooking oil on the spray behavior and macroscopic spray characteristics. To analyze quantitative characteristics of test fuels, injection quantity was measured at various injection pressures and the spray images of injected fuels in the pressurized chamber were obtained by using a high speed camera and image analysis system. Based on the measured spray images, the spray tip penetration and spray cone angle were investigated at various energizing timings and injection pressures. In this work, the experimental results showed that the injection quantity of waste cooking biodiesel indicated the higher quantities than diesel at high injection pressure. As the injection pressure was increased, the spray tip penetrations of biodiesel were higher value than diesel. The difference of penetration between biodiesel and conventional diesel fuel was reduced in accordance with the increase of injection pressure. Also, the spray angles of diesel were larger than that of biodiesel because diesel fuel has lower viscosity than biodiesel. In addition, the spray evolution processes of biodiesel fuel at various injection pressures and the elapsed time after the injection were compared to the conventional diesel fuel.

• 한국항해항만학회:학술대회논문집
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• 한국항해항만학회 2022년도 추계학술대회
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• pp.160-161
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• 2022

Hydrogen is bridge fuel with high energy content and environmentally friendly to satisfy the stringent IMO regulation relating to greenhouse gas (GHG) emissions. There is growing interest in hydrogen in numerous nations and regions illustrated by an extensive range of research and development in technology. Regarding maritime applications, researchers have recognized the utilization of hydrogen as a fuel for fuel cells, a device that converts the chemical energy of the fuel to electrical energy. Solid oxide fuel cell (SOFC), with high working temperature, is easy to combine with the waste heat recovery cycles/devices to increase output power and thermodynamic performances as well. Furthermore, the cold energy from liquid hydrogen supplied to SOFC can also be used to generate more power. In this study, we proposed a SOFC integrated system with the idea of combining the waste heat recovery from the SOFC exhaust stream and cold energy utilization from LH₂. The designation is aimed to target small-scale vessel which uses electric propulsion for short distances voyage.

• 방사성폐기물학회지
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• 제2권3호
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• pp.219-230
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• 2004

Most of the low-level liquid radioactive wastes generated from PWR plants are classified into high or low total suspended solid(HTDS or LTDS), and into radiochemical and radioactive laundry waste. Although the evaporation process has a high decontami- nation ability, it has several problems such as corrosion, foam, and congestion. A new liquid waste disposal process using the ion-exchange demineralizer(IED), instead of the current evaporation process, has been introduced into the Yonggwang NPP #5 and 6. These two methods have been compared to understand the differences in this study. Aspects compared here were the released radioactivity amount of the liquid radioactive wastes, the dose of off-site residents, the decontamination factor, and the amount of the solid radioactive wastes. The IED system is designed to discharge higher radioactivity about 20% than the evaporating system, and the actual radioactivity released from the evaporating and IED system were 0.473mCi and 1.098mCi, respectively. The radioactivity released from the IED was 2.32 times higher than that of the evaporating system. The dose of off-site residents was $2.97{\times}10^{-6}$mSv for the evaporating system, and $6.47{\times}10^{-6}$mSv for IED. The decontamination factor(DF) of the evaporator is, in most cases, far lower than the lower limits of detection(LLD) with the Ge-Li detector. Due to the low concentration of the liquid wastes collected from the liquid waste system, the decontamination factor of IED is very low. Since there is not enough data on the amount of solid radioactive wastes generated by the evaporation system, the comparison on these two systems has been conducted on the basis of the design, and the comparison result was that the evaporating system generated more wastes about 40% than IED.

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

• 한국산학기술학회논문지
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• 제10권12호
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• pp.3761-3767
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• 2009

산업단지에서 발생하는 액상폐기물(폐유와 폐유기용제)을 고온반응기에서(온도 $1,250{\sim}1,400^{\circ}C$, 압력 1기압) 연소시키면서 연소 특성, 유해물질 분해정도 및 연소 후 배출가스 특성 등을 살펴보았다. 산소와 폐기물의 질량비($O_2$/waste mass fraction)가 1.53 이하로 줄어들 때 반응기는 산화분위기에서 환원분위기로 전환되었고 연소 후 배출가스는 NOx 배출량이 감소하고 합성가스의 발생비율이 증가하였으며 BTEX류는 99.99%이상 분해되는 것으로 나타났다. 본 연구에서 제안한 시스템 및 조업조건 하에서 고농도의 액상폐기물(폐유와 폐유기용제)을 처리한 결과 미량 오염물질의 배출농도는 매우 낮은 값을 보여 액상폐기물의 처리에 적합한 것으로 판단되며 또한 연소 후 합성가스도연료로 활용할 수 있을 것으로 사료된다.

• 공업화학
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• 제8권1호
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• pp.99-107
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• 1997

핵연료분말 변환공정 중 우라늄 정광의 용해/정제 및 가공공정에서 발생하는 폐액의 처리에 대한 연구가 수행되었다. 우라늄 정광의 용해/정제공정에서 발생된 폐액은 pH 1 이하의 강산성으로 AUC 분말 제조공정에서 발생된 폐액 중의 우라늄을 ADU 형태로 회수한 후 발생된 2차 여액 속의 미세 ADU 입자 용해를 위해 사용된다. 2차 여액 속의 미세 ADU 입자들의 용해를 위해 용해/정제 공정의 폐액을 사용해서 pH 4로 전처리한 후, lime을 이용하여 pH 9.2로 30분 정도 반응시킬 경우 여액 중의 우라늄 농도를 3ppm 이하로 처리할 수 있었다. 가공 폐액은 미세 oil droplet들이 emulsion 형태로 발생하며, 약 300ppm의 우라늄 농도를 나타내었다. 먼저, emulsion을 파괴시키는 방법은 질산을 가하여 급속가열시키는 것이 효과적이었다. Emulsion 파괴 후 1mole NaOH를 가하여 $Na_2U_2O_7$형태로 우라늄을 회수하였으며, pH11.5에서 최적 처리조건을 나타내었으나 최종 여액 중의 우라늄 농도는 5ppm을 나타냈다. 여액 중의 우라늄 농도를 최소화하기 위해 lime으로 처리하는 방법이 연구되었으며, 가공폐액을 직접 lime 처리하기 위해 4N 질산으로 emulsion을 파괴 시킨 후, pH 1.6에서 lime을 1.5g/100ml로 반응시킬 경우 여액 중의 우라늄 농도를 1ppm까지 낮출 수 있었다. 한편, 경수로형 분말 제조공정 중 우라늄 회수공정에서 발생된 폐액 중의 미량 우라늄은 NaOH를 가하여 우라늄을 침전시킨 결과, $Na{\cdot}U{\cdot}F{\cdot}NH_4$등이 혼합된 침전물이 얻어졌으며, 여과후 상등액에서는 우라늄은 감지할 수 없었다.