• 공업화학
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• 제16권1호
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• pp.28-33
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• 2005

본 연구는 재자원화 기술개발의 일환으로 폐기물 생선내장으로부터 아미노산을 회수하기 위하여 아임계 및 초임계 가수분해반응을 수행하였다. 반 회분식 및 회분식 반응기를 이용하여 아미노산의 최적수율에 영향을 미치는 온도, 시간 등의 반응인자에 대한 영향에 관하여 연구하였다. 회분식 반응결과, 폐기물 생선내장으로부터 얻어진 전체적인 아미노산의 최적수율(137 mg/g-dry entrails)은 온도 $250^{\circ}C$ (p=4 MPa), 반응시간 60 min에서 얻을 수 있었다. 초임계조건(e.g., T=$400^{\circ}C$, P=45 MPa)에서는, 아미노산의 생성속도보다 분해속도가 빠른 관계로 수율이 감소하는 경향을 나타내었다. 본 연구결과 고수율의 아미노산을 생성하기 위해서는 저온 및 짧은 반응시간에서의 조작이 필요한 것을 알았다.

• Environmental Engineering Research
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• 제11권6호
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• pp.311-317
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• 2006

Feasibility of destroying synthetic and actual leachate containing humic acids and ammonia compounds by supercritical water oxidation (SCWO) was evaluated. In this study, destruction efficiencies of humic acids and ammonia respectively were investigated at various reaction temperatures and residence times under pressure a supercritical pressure (280 atm). To lower reaction temperature, chemical oxidants were used. The experiment was carried out in a cylindrical batch reactor made of Hastelloy C-276 that can withstand high temperature and pressure. Concentrations of humic acids and ammonia were measured using a $COD_{Cr}$ method and an ammonia selective electrode, respectively. The optimal destructive condition of humic acids in the presence of stoichiometric oxygen(air) was 3 min at $380^{\circ}C$, but the temperature could be lowered to subcritical region ($360^{\circ}C$) along with $H_2O_2$ as an oxidant. For ammonia, the optimal destructive condition with air was 5 min at $660^{\circ}C$, but it was possible to operate the process for 3 minutes at $550^{\circ}C$ or 2 min at $600^{\circ}C$ along with $H_2O_2$ as an oxidant. At 2 min and $550^{\circ}C$ along with $H_2O_2$ as an oxidant, humic and ammonia compounds in the actual leachate were easily destructed and the effluent quality met the Korea Standard Leachate Quality.

• Korean Chemical Engineering Research
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• 제50권4호
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• pp.678-683
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• 2012

세리아 미세입자는 자동차, 석유공정, 폐수처리 등 다양한 분야에서 촉매로서 널리 쓰이고 있는 중요한 물질이다. 이제까지, 세리아 미세입자를 제조하기 위한 다양한 제조법이 연구되었는데, 본 연구에서는 짧은 반응시간과 간단한 공정이 가능한 초임계 메탄올을 이용하는 입자 제조 공정을 통해 세리아 나노입자를 제조하였다. 회분식 반응기를 이용하여 짧은 시간 안에 세리아 나노입자를 제조하는데 성공하였다. 초임계 메탄올을 이용하여 세리아 나노입자를 제조하는 경우, 다른 첨가제 없이도 약 6 nm의 크기를 갖는 나노입자를 합성할 수 있었다. 이 크기는 같은 온도와 압력조건의 초임계수를 이용하여 표면개질제 없이 합성한 입자보다 훨씬 작은 크기이다. 이는 초임계수와 초임계 메탄올의 밀도 차이와, 초임계 메탄올에서의 세리아 표면에서 일어나는 결정성장을 제한하는 반응, 그리고 초임계 메탄올과 초임계수의 임계점의 차이에서 기인하는 것이다. 또한 여러 가지 유기물을 표면개질제로 첨가하여 표면을 개질한 세리아 나노입자를 제조하였으며, FT-IR과 HR-TEM, TGA를 통해 이를 확인할 수 있었다. 표면을 개질한 세리아 나노입자는 표면개질을 하지 않은 세리아 나노입자와는 다르게, 유기용매에 대한 분산성이 뛰어났으며, 표면개질제로 사용하는 유기물의 양과 종류를 조절함으로써 세리아 나노입자의 크기와 모양을 조절할 수 있었다.

• Korean Chemical Engineering Research
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• 제46권4호
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• pp.747-751
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• 2008

수분이나 유리지방산 함량이 높은 폐식용유의 적용 가능성을 알아보기 위하여 초임계메탄올을 이용한 바이오디젤 연료의 합성에서 첨가물이 미치는 영향에 대해 실험하였다. 회분식 반응기를 이용하여 물, 유리지방산, 항산화물질의 함량을 달리하여 전이에스테르화반응을 진행하였고, 기체크로마토그래피를 이용해 시료에 포함된 지방산메틸에스테르의 양을 측정하였다. 수분이 증가함에 따라 생성되는 지방산메틸에스테르의 함량이 약간 감소했으나 염기촉매나 산촉매에 비해서는 그 폭이 아주 작았다. 유리지방산, 비타민 E, ${\beta}$-카로틴의 함량 변화에 따른 영향은 거의 없었다.

• 방사성폐기물학회지
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• 제7권3호
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• pp.175-182
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• 2009

유동층 비중차 분리기를 이용하여 혼합 폐 이온교환수지에서 폐 양이온수지와 폐 음이온수지로 분리하였으며, 원소분석과 열분석으로 분리가 잘 되었음을 확인하였다. 비중차 분리를 통해 얻은 수백 미크론의 구형 알갱이 형태의 폐 양이온수지와 폐 음이온수지 각각을 볼밀로써 24시간 습식 분쇄하여 적정 입도 이하의 입자가 균일하게 분산된 고농도 슬러리를 얻은 다음, 희석하여 $COD_{cr}$, 농도 25,000ppm의 시료를 준비하였다. 실험실 규모의 소형 초임계수산화(Super Critical Water Oxidation, SCWO) 장치(반응기 용량 : 220 mL)로써 화력발전소에서 발생한 폐 양이온수지와 폐 음이온수지에 대해 최적의 분해조건을 확립한 다음, 파일럿플랜트(반응기 용량 : 24 L)로 scale-up 실험을 수행하였다. 우선 화력발전소의 폐수지로서 파일럿테스트를 실시한 다음, 원자력발전소의 폐수지로써 파일럿테스트를 수행하여 최적의 분해조건을 설정하였다. 실험실 규모의 소형 SCWO 장치와 파일럿플랜트의 설계 및 운전에서 얻은 경험을 바탕으로 원자력발전소 내에 설치 가능한 규모로 상용설비(처리용량 : 150kg/h)를 설계 중에 있다.

• Korean Chemical Engineering Research
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• 제43권2호
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• pp.318-323
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• 2005

초임계수 산화는 난분해성 유기화합물의 분해를 위한 공정으로 각광받고 있다. 본 연구에서는 연속반응기에서 온도 $387-500^{\circ}C$, 압력 250 bar의 초임계수 조건하에서(EDTA 분해효율) 체류시간 15.9-88.9초의 범위의 EDTA 분해효율을 측정하였다. 이때 산화제로는 과산화수소($H_2O_2$)를 사용하였다. EDTA의 분해효율은 온도 및 산화제투입량의 증가에 따라 상승하였으며, 반응물 도입유속의 감소 즉, 체류시간의 증가에 따라서 상승하였다. 본 연구결과 온도 $500^{\circ}C$, 압력 250 bar, 산화제 투입량 400%의 조건에서 최대 99.6%의 분해효율을 나타내었다. 분해효율에 미치는 온도의 영향이 산화제 투입량 증가의 영향보다 컸으며, 5,000 mg/L의 EDTA($COD_{Cr}$로서 3,063 mg/L)의 99% 이상 분해효율은 온도 $500^{\circ}C$와 압력 250 bar의 초임계수 산화조건에서 산화제투입량 200% 이상 및 체류시간 40.1초 이상에서 얻을 수 있었다.

• Nuclear Engineering and Technology
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• 제36권5호
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• pp.403-414
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• 2004

An experimental study of heat transfer characteristics near the critical pressure has been performed with an internally-heated vertical annular channel cooled by R-134a fluid. Two series of tests have been completed: (a) steady-state critical heat flux (CHF) tests, and (b) heat transfer tests for pressure reduction transients through the critical pressure. In the present experimental range, the steady-state CHF decreases with increase of the system pressure for fixed inlet mass flux and subcooling. The CHF falls sharply at about 3.8 MPa and shows a trend towards converging to zero as the pressure approaches the critical point of 4.059 MPa. The CHF phenomenon near the critical pressure does not lead to an abrupt temperature rise of the heated wall, because the CHF occurs at remarkably low power levels. In the pressure reduction transients, as soon as the pressure passes below the critical pressure from the supercritical pressure, the wall temperatures rise rapidly up to very high values due to the departure from nucleate boiling. The wall temperature reaches a maximum at the saturation point of the outlet temperature, and then tends to decrease gradually.

• Nuclear Engineering and Technology
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• 제54권3호
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• pp.842-848
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• 2022

Parametric studies of heat transfer and fluid flow are very important research of interest because the design and operation of fluid flow and heat transfer systems are guided by these parametric studies. The safety of the system operation and system optimization can be determined by decreasing or increasing particular fluid flow and heat transfer parameter while keeping other parameters constant. The parameters that can be varied in order to determine safe and optimized system include system pressure, mass flow rate, heat flux and coolant inlet temperature among other parameters. The fluid flow and heat transfer systems can also be enhanced by the presence of or without the presence of particular effects including gravity effect among others. The advanced Generation IV reactors to be deployed for large electricity production, have proven to be more thermally efficient (approximately 45% thermal efficiency) than the current light water reactors with a thermal efficiency of approximately 33 ℃. SCWR is one of the Generation IV reactors intended for electricity generation. High Performance Light Water Reactor (HPLWR) is a SCWR type which is under consideration in this study. One-eighth of a proposed fuel assembly design for HPLWR consisting of 7 fuel/rod bundles with 9 coolant sub-channels was the geometry considered in this study to examine the effects of system pressure and mass flow rate on wall and fluid temperatures. Gravity effect on wall and fluid temperatures were also examined on this one-eighth fuel assembly geometry. Computational Fluid Dynamics (CFD) code, STAR-CCM+, was used to obtain the results of the numerical simulations. Based on the parametric analysis carried out, sub-channel 4 performed better in terms of heat transfer because temperatures predicted in sub-channel 9 (corner subchannel) were higher than the ones obtained in sub-channel 4 (central sub-channel). The influence of system mass flow rate, pressure and gravity seem similar in both sub-channels 4 and 9 with temperature distributions higher in sub-channel 9 than in sub-channel 4. In most of the cases considered, temperature distributions (for both fluid and wall) obtained at 25 MPa are higher than those obtained at 23 MPa, temperature distributions obtained at 601.2 kg/h are higher than those obtained at 561.2 kg/h, and temperature distributions obtained without gravity effect are higher than those obtained with gravity effect. The results show that effects of system pressure, mass flowrate and gravity on fluid flow and heat transfer are significant and therefore parametric studies need to be performed to determine safe and optimum operating conditions of fluid flow and heat transfer systems.

• 방사선산업학회지
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• 제9권4호
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• pp.217-221
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• 2015

When reactor coolant leaks occur due to cracks of a steam generator's tube, radioactive materials contained in the primary cooling water in nuclear power plant are forced out toward the secondary systems. At this time the secondary water purification resin in the ion exchange resin tower of the steam generator blowdown system is contaminated by the radioactivity of the leaked radioactive materials, so we pack this in special containers and store temporarily because we could not dispose it by ourselves. If steam generator tube leakage occurs, it produces contaminated spent resins annually about 5,000~7,000 liters. This may increase the amount of nuclear waste productions, a disposal working cost and a unit price of generating electricity in the plant. For this reasons, it is required to develop a decontamination process technique for reducing the radioactive level of these resins enough to handle by the self-disposal method. In this research, First, Investigated the structure and properties of the ion exchange resin used in a steam generator blowdown system. Second, Checked for a occurrence status of contaminated spent resin and a disposal technology. Third, identified the chemical characteristics of the waste radionuclides of the spent resin, and examined ionic bonding and separation mechanism of radioactive nuclear species and a spent resin. Finally, we carried out the decontamination experiment using chemicals, ultrasound, microbubbles, supercritical carbon dioxide to process these spent resin. In the case of the spent resin decontamination method using chemicals, the higher the concentration of the drug decontamination efficiency was higher. In the ultrasound method, foreign matter of the spent resin was removed and was found that the level of radioactivity is below of the MDA. In the microbubbles method, we found that the concentration of the radioactivity decreased after the experiment, so it can be used to the decontamination process of the spent resin. In supercritical carbon dioxide method, we found that it also had a high decontamination efficiency. According to the results of these experiments, almost all decontamination method had a high efficiency, but considering the amounts of the secondary waste productions and work environment of the nuclear power plant, we judged the ultrasound and supercritical carbon dioxide method are suitable for application to the plant and we established the plant applicable decontamination process system on the basis of these two methods.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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• pp.15-20
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• 1997

We present the results HELIOS verification against VENUS PWR critical experiments loaded with high plutonium content mixed oxides fuels. The effective multiplication factors are calculated to be slightly supercritical within an acceptable error bound. In the prediction of power shape, HELIOS results are in close agreement with the measured values. The RMS errors of re-normalized calculated fission rate distribution are less than 1.4 % with either explicit or implicit models or micro tubes/rods in each fuel assembly for both ALL-MOX and GD-MOX mock-up cores.