• Clean Technology
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• v.30 no.1
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• pp.37-46
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• 2024

Environmental problems caused by plastic waste have been continuously growing around the world, and plastic waste is increasing even faster after COVID-19. In particular, PP and PE account for more than half of all plastic production, and the amount of waste from these two materials is at a serious level. As a result, researchers are searching for an alternative method to plastic recycling, and plastic pyrolysis is one such alternative. In this paper, a numerical study was conducted on the pyrolysis behavior of non-condensable gas to predict the chemical reaction behavior of the pyrolysis gas. Based on gas products estimated from preceding literature, the behavior of non-condensable gas was analyzed according to temperature and residence time. Numerical analysis showed that as the temperature and residence time increased, the production of H₂ and heavy hydrocarbons increased through the conversion of the non-condensable gas, and at the same time, the CH₄ and C₆H₆ species decreased by participating in the reaction. In addition, analysis of the production rate showed that the decomposition reaction of C₂H₄ was the dominant reaction for H₂ generation. Also, it was found that more H₂ was produced by PE with higher C₂H₄ contents. As a future work, an experiment is needed to confirm how to increase the conversion rate of H₂ and carbon in plastics through the various operating conditions derived from this study's numerical analysis results.

• Proceedings of the Korea Air Pollution Research Association Conference
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• 2003.05b
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• pp.379-380
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• 2003

연소나 폐기물 감량화 처리를 위해 이루어지는 소각과정에서 방출되는 대기오염물질은 소각재의 다양한 특성으로 인해 배출물의 특성파악이 매우 어렵고 그로 인해 제어에 많은 어려움을 겪고 있다. 연소 혹은 소각과정에서 에어로졸을 제어하는 것은 대기 중에서 발견되는 중금속성분을 근본적으로 줄이는 기본적인 조치로서 상당히 중요한 역할을 한다(Natusch and Wallace, 1974; Oppelt, 1986; Oberdorster et al., 1995). 본 연구에서는 소각공정에서 금속성 에어로졸 형태로 배연기체 중에 혼합되어 배출되는 여러 가지 금속성분 중 양적으로 많이 배출되는 납성분의 제어를 위한 기초연구를 수행하였다. (중략)

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.367-372
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• 1996

석탄화력발전소의 산업부산물인 fly ash를 이용한 폐흡착재의 붕규산유리고화가 능성을 분석하였다. 폐흡착재는 기체상의 세슘이나 루테늄 등을 포집한 후에 발생되는 필터류 등의 고체폐기물을 말하며 본 실험에서는 CsNO$_3$와 fly ash를 몰비로 1.5 : 1 되게 섞어 1200 $^{\circ}C$에서 1시간 가소 시킨 후에 생성되는 pollucite를 모의폐흡 착재로 사용하였다. 폐흡착재를 무게비 15 ~ 30 %로 fly ash, SiO$_2$, $Na_2$CO$_3$, B$_2$O$_3$와 혼합한 후 1150 $^{\circ}C$에서 3시간 용융시켜 붕규산유리화시켰다. 제조된 붕규산유리고화체의 침출성을 평가하기 위하여 2일동안의 soxhlet 침출실험을 수행하였다. 한편 폐흡착재의 붕규산유리고화과정을 알아보기 위하여 붕규산유리고화체의 원료물질에 대하여 유리화과정과 동일한 조건하에서 TG/DTA분석을 수행하였다.

• Proceedings of the Korea Air Pollution Research Association Conference
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• 2001.11a
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• pp.223-224
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• 2001

고온 소각공정은 산업용 및 가정용 폐기물의 처리시 부피의 현격한 감소뿐만 아니라 유해성 유기물을 무해한 형태로 전환시켜 주는 장점을 지니고 있다. 그러나 유해 중금속의 경우 소각공정 중 소멸되거나 새로이 생성되지 않고 화학적, 물리적 변형만 일어날 뿐, 그 유해성은 소멸되지 않고, 고온 휘발성 유해중금속의 경우 일부 환경으로 배출되므로 잠재적으로 심각한 대기오염원이 되고 있다(1990). 최근에는 이러한 고온 휘발성 중금속의 효과적인 제거를 위한 연구로 여러 가지 무기질 흡착제를 이용한 고온 흡착제거 연구가 활발히 이루어지고 있다(1998, 1999). (중략)

• Journal of the Korean Recycled Construction Resources Institute
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• v.11 no.3
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• pp.260-266
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• 2023

In recent years, excessive emissions of carbon dioxide(CO₂) have become the cause of global climate change. Consequently, there has been significant research activity aimed at both removing and utilizing CO₂. This study assesses the potential utilization of railway tie concrete waste, generated from railway infrastructure, as a CO₂ absorption material and investigates the physicochemical properties before and after CO₂ absorption to understand the CO₂ removal mechanisms. Railway tie concrete waste primarily consists of Si(26.60 %) and contains 9.82 % of Ca. Compared to samples of Cement and Normal concrete waste, it demonstrated superior potential for use as a CO₂ absorption material, with approximately 98 % of the Ca content participating in CO₂ absorption reactions. Through Thermogravimetric Analysis(TGA) and X-ray Diffraction(XRD) analysis, it was confirmed that the carbonate reaction, where the Ca in railway tie concrete waste converts into CaCO₃ through reaction with CO₂ gas, is the primary mechanism for CO₂ removal. Furthermore, Scanning Electron Microscopy(SEM) analysis revealed the formation of numerous CaCO₃ particles with sizes less than 0.1 ㎛ after the CO₂ absorption reaction. This transformation of large internal voids in the CO₂ absorption material into mesopores resulted in an increase in the specific surface area of the material.

• Clean Technology
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• v.14 no.2
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• pp.110-116
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• 2008

The radioactive wastes generated from the nuclear industry can be divided into the forms of solid, liquid, or gas. Radioactive methyl iodide, a gaseous radioactive waste, is absorbed by activated carbon with 5 wt% of Trietylenediamine (1,4-diazania-bicycle[2.2.2]octane, TEDA) impregnated on the surface. Methyl Iodide ($CH_3I$) is combined chemically with TEDA (the final product : I-TEDA). To recycle radioactive activated carbon, removal of I-TEDA from activated carbon is needed. A wet method for recycling impregnated active carbon was developed to remove radioactive I-TEDA using an acetonitrile solution, which produces lots of secondary wastes. We suggest the removal of I-TEDA by supercritical carbon dioxide with co-solvents. In this experiment, we used a quartz crystal microbalance (QCM) for measuring the removal rate of the I-TEDA. From the experimental results, methanol was found to be the optimum co-solvent, and the optimum conditions such as temperature, pressure, and co-solvent flow rate were obtained. Possibility of using supercritical fluid in the removal of I-TEDA from radioactive activated carbon was also discussed.

• 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.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.2 no.3
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• pp.165-174
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• 2004

In order to simultaneously vitrify the ion exchange resin(IER) and combustible dry active waste(DAW) generated from Korean nuclear power plants, a vitrification pilot test was conducted using an induction cold crucible melter(CCM) . The energy necessary for startup of the glass using a Ti-ring was evaluated as about 290 kWh. The power supplied from a high frequency generator to melt the glass properly was ranged from 160 to 190 kW without any interruption. When the mixture of the IER and DAW was fed into the CCM, the concentration of CO was lowered up to 1/40 compared to feeding the IER solely. It may be caused by the DAW which can produce about 1.8 times higher heat compared to the IER. When the swelling phenomenon occurred in the glass melt, the concentration of $NO_2$, oxidizing gas, was higher than NO, reducing gas. Total feed amounts of the IER and DAW were 368 and 751 kg, respectively. And then, about 74 of volume reduction factor was achieved.

• Nuclear Engineering and Technology
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• v.27 no.5
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• pp.767-774
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• 1995

Behavior of radionuclides such $^{60}$ Co, $^{54}$ Mn and $^{137}$ Cs in the incineration Process was Studied by trial burns of simulated wastes with radio-isotope tracers. Behavior of nonvolatiles, $^{60}$ Co and $^{54}$ Mn, was similar to that of particulate matters in the process. Decontamination factors(DFs) for $^{60}$ Co and $^{54}$ Mn were 4.7$\times$10$^{5}$ and 6.2$\times$10$^{5}$ , respectively. Behavior of semivolatile radio-isotope, $^{137}$ Cs, was temperature dependent. DFs for $^{l37}$Cs at In different incineration temperature of 85$0^{\circ}C$ and $700^{\circ}C$ were 2.8$\times$10$^3$ and 2.6$\times$10$^4$, respectively. Trial bums of dry active waste(DAW) transported from nuclear power station(NPS) Kori 3,4 were also performed. DF for gross $\beta$/${\gamma}$ radioactivity in DAW was 1.1$\times$10$^{5}$ . This was a little higher than the estimated value, which was calculated from the tracer test results and nuclides distribution in the DAW. Average emission concentration was 0.019 Bq/N $m^3$, which could meet the maximal permissible concentration(MPC) in stack emission.n.

• 한국신재생에너지학회:학술대회논문집
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• 2010.11a
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• pp.152.2-152.2
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• 2010

LFG는 매립된 폐기물 중 유기성분이 혐기성조건에서 미생물에 의해 분해가 되면서 발생하며, 이러한 매립지가스는 주변 지역의 자연 및 생활환경에 악영향을 미치기 때문에 소각 등의 방법으로 LFG를 처리하고 있다. 일반적으로 매립지로부터 발생하는 가스의 량은 폐기물 1톤 당 $150{\sim}250m^3$로서 매립 후 2~3년 후에 최대량이 발생하며 매립 후 20~30년 후까지 지속적으로 발생함으로 안정적인 LFG의 공급이 가능하며, 메탄함량이 50%인 경우 약 $5,000kcal/m^3$의 높은 발열량을 가지므로 대체에너지원으로 이용할 경우 환경적인 문제 해결 및 신재생에너지원으로 활용할 수 있다. LFG 자원화 할 경우 가장 안정적인 방안으로 발전 및 중질가스로 활용하는 것이나, 발전의 경우 최소 200만톤 이상의 매립용량을 갖추어야 경제적인 사업성을 확보할 수 있으며, 중질가스로 활용하는 경우 인근에 가스 수요처를 확보해야 하는 어려움이 있다. 만약 중 소규모의 매립장에서 발생하는 LFG를 안전하고 경제적인 조건으로 저장 및 수송할 수 있다면 중 소규모의 매립지에서 발생하는 LFG도 활용할 수 있을 것으로 기대되며, 안전하고 경제적인 저장과 수송기술을 통하여 발전이 아닌 중질가스로의 활용도 가능하게 될 것이다. 또한 여러 곳의 매립장에서 발생한 LFG를 한 곳으로 집중시켜 고질가스로 전환하는 설비비용을 절감할 수 있으며, 정제된 고질가스를 이용하여 발전보다 경제적인 자동차 연료나 도시가스로 활용할 수 있을 것이다. 본 연구에서는 LFG의 저장과 수송기술 중 GTS 기술을 통하여 저장과 수송에 제약이 크고 많은 비용이 소비되는 기체 상태의 에너지원을 하이드레이트화 시킴으로서 중 소규모 매립지에서 상대적으로 적은 비용으로 가스저장과 지상수송이 가능하게 할 수 있다. 본 연구의 결과로 LFG 에너지화 실증화 플랜트를 설계/제작 하였으며, 메탄+이산화탄소+물 하이드레이트 형성 실험 결과 4.56 Mpa, 277.2 K 조건에서 3시간을 한 사이클로 하는 공정운전을 가지는 것을 확인하였다. 이때 생성된 슬러리상의 하이드레이트를 고압으로 배출하여 펠릿으로 형성시켰으며, 형성된 하이드레이트 펠릿의 경우 92.27%의 메탄을 포함하는 것을 확인하였다.