• Title/Summary/Keyword: Chemical Reactor

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Decomposition Characteristics of Cyano-compounds in Non-thermal Packed-Bed-Plasma-Reactor (충전형 저온 플라즈마 반응기에서 시안 화합물의 분해 특성)

  • Ryu, Sam-Gon;Park, Myung-Kyu;Lee, Hae-Wan
    • Korean Chemical Engineering Research
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    • v.50 no.2
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    • pp.343-347
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    • 2012
  • The decomposition behaviors of gaseous cyanides in non-thermal plasma-catalyst hybrid reactor have been investigated with the variation of discharge power, influent concentration of cyanide, humidity of air carrier and packed materials in the reactor. Destruction of cyanides by plasma only process was very difficult compared to that of trichloroethylene. But the destruction efficiencies of cyanides were dramatically improved through packing alumina or Pt/alumina bead in the plasma discharge region. From the results, it could be assumed that thermal catalytic effect is involved simultaneously with plasma in the reaction of cyanides destruction on the alumina or Pt/alumina packed plasma reactor.

Hydrogen Separation and Production using Proton-Conducting Ceramic Membrane Catalytic Reactors (프로톤 전도성 세라믹 멤브레인 촉매 반응기를 이용한 수소 분리 및 제조 기술)

  • Seo, Minhye;Park, Eun Duck
    • Korean Chemical Engineering Research
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    • v.57 no.5
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    • pp.596-605
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    • 2019
  • Proton-conducting perovskite ceramic materials are highly promising for solid electrolytes as well as catalysts at high temperatures. Therefore, they possess an outstanding potential for the membrane reactor in which both reaction and separation occur at a same time. Especially, in the case of hydrogen production catalyst, hydrogen separation, and the membrane reactor coupled with catalyst and separation, extensive results have been reported on the effect of the dopant in the solid electrolytes, temperature, and composition of reactants on the performance. In this review, the recent research trend on the application of proton-conducting ceramic materials to hydrogen production catalyst, hydrogen separation, and membrane reactor is surveyed. Moreover, the potential application and prospect of these materials to the next-generation hydrogen production and separation is discussed.

A Study of Prevention of Pipe Scale with Cu-Zn Metal Fiber (Cu-Zn Metal Fiber를 이용한 배관 스케일 방지에 관한 연구)

  • Lee, Sang-Ho;Kim, Jong-Hwa;Song, Ju-Yeong
    • Journal of the Korean Applied Science and Technology
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    • v.27 no.1
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    • pp.70-75
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    • 2010
  • Scale generation in the inside of a pipe IS restricted by reduction and oxidation(REDOX) reaction of alloyed metal of Cu-Zn. To measure the scale generating rate in the 1.67 mm of inside diameter of stainless steel tube, 300 ppm of $CaCO_3$ solution is circulated in the REDOX reactor and stainless steel tube in the order. In the case of $CaCO_3$ solution treated by REDOX reactor, flowing is maintained without plugging in the stainless steel tube, and the concentration of Cu and Zn in the circulating solution showed less than 1 ppm, which is equal to that of untreated by REDOX reactor. The crystal type of $CaCO_3$ generated by crystalline nucleus of Cu or Zn, mostly showed aragonite type.

Simulation of the Hydrogen Conversion Rate Prediction for a Solar Chemical Reactor (태양열 화학반응기의 수소전환효율 예측 시뮬레이션)

  • Ko, Jo-Han;Seo, Tae-Beom
    • 한국태양에너지학회:학술대회논문집
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    • 2008.11a
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    • pp.294-299
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    • 2008
  • Steam reforming of methane is the most wide spread method for hydrogen production. It has heed studied more than 60 years. methane reforming has advantages in technological maturity and economical production cost. Using a high-temperature solar thermal energy is an advanced technology in Steam reforming process. The synthesis gas, the product of the reforming process, can be applied directly for a combined cycle or separated for a hydrogen. In this paper, hydrogen conversion rate of a solar chemical reactor is calculated using commercial CFD program. 2 models are considered. Model-1 is original model which is designed from the former researches. And model-2 is ring-disk set of baffle is inserted to enhance the performance. The solar chemical reactor has 3 inlet nozzle at the bottom of the side wall near quartz glass and an exit is located at the top. Methane and steam is premixed with 50:50 mole fraction and goes into the inside. Passing through the porous media, the reactants are conversed into hydrogen and carbon monoxide.

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Dynamic Simulation of Membrane Reactor for WGS Reaction (Water Gas Shift (WGS) 공정에 대한 분리막 반응기의 동적 모사)

  • Oh, Min;Yi, Yong;Hong, Seong-Uk
    • Membrane Journal
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    • v.20 no.3
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    • pp.228-234
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    • 2010
  • In this study, dynamic simulation of membrane reactor was performed for water gas shift reaction and temperature, hydrogen concentration, etc. were investigated as a function of time and position. Simulation results indicated that differences of hydrogen concentration, hydrogen partial pressure, and temperature in the radial direction, were larger in the entrance than in the exit. In addition, the hydrogen flux was the largest in the entrance, where the hydrogen partial pressure difference was the largest, and the conversion of carbon monoxide in the exit was about 0.65.

Hydrogen and Carbon Black Production by Pyrolysis of Natural Gas (천연가스 열분해에 의한 수소 및 카본 생산)

  • Yoon, Y.H.;Park, N.K.;Lee, T.J.;Chang, W.C.;Lee, B.G.;Ahn, B.S.
    • Transactions of the Korean hydrogen and new energy society
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    • v.14 no.2
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    • pp.105-113
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    • 2003
  • The pyrolysis for production of hydrogen and high quality carbon black from natural gas were studied. The reactivities in tubular reactor and FVR(free volume reactor) for the methane pyrolysis were compared, in order to prevent the formation of undesirable carbon product such as pyrocarbon, the FVR was designed. The hydrogen yield and the formation of carbon black from methane pyrolysis in this reactor were investigated at temperature range between 1443 and 1576K. From the result of TEM (transmission electron microscopy) analysis, it was confirmed that the CFC(catalytic filamentous carbon) was formed without pyrocarbon.

Corrosion Damage Behavior of STS 304 and STS 415 for Reactor Coolant Pump during Ultrasonic-Chemical Decontamination Process (원자로 냉각재 펌프용 STS 304와 STS 415의 초음파-화학제염 공정 시 부식 손상 거동)

  • Hyeon, Gwang-Ryong;Park, Jae-Cheol;Han, Min-Su;Kim, Seong-Jong
    • Journal of the Korean institute of surface engineering
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    • v.51 no.4
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    • pp.218-223
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    • 2018
  • In this study, we proposed a new ultrasonic-chemical decontamination process for decontaminating radioactive corrosion products during the maintenance of reactor coolant pump (RCP). The actual decontamination process was reproduced in the laboratory. And the corrosion characteristics of stainless steel (STS), constituting the RCP interior parts, were examined. The weight-loss measurment and polarization experiment were carried out in order to determine the corrosion characteristics of STS 304 and STS 415 by repeated decontamination processes. The STS 304 presented a little corrosion damage, which was almost indistinguishable from visual observation. The weight-loss rate of STS 304 was also significantly lower. On the other hand, STS 415 showed severe corrosion damage on its surface, greater weight-loss rate and higher corrosion current density than STS 304.

Study on the Deactivation Trends of Liquid Fuel According to the Types of Endothermic Catalyst in Flow Reactor (흐름형 반응기 내에서 액체연료의 흡열반응촉매 종류에 따른 비활성화 정도에 대한 연구)

  • Lee, Tae Ho;Jeon, Sunbin;Kim, Sung Hyun;Jeong, Byung Hun;Han, Jeong Sik
    • Journal of the Korean Society of Propulsion Engineers
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    • v.22 no.5
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    • pp.81-87
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    • 2018
  • In hypersonic aircraft, increase of aerodynamic and engine heat lead thermal load in airframe. It could lead structural change of aircraft's component and malfunctioning. Endothermic fuels are liquid hydrocarbon fuels which absorb the heat load by undergoing endothermic reactions. In this study, we investigated the relationship between product, coke formation and catalytic properites of endothermic catalysts by using exo-tetrahydrodicyclopentadiene as a fuel in a fixed bed flow reactor similar to the actual reaction conditions.

The corrosion of aluminium alloy and release of intermetallic particles in nuclear reactor emergency core coolant: Implications for clogging of sump strainers

  • Huang, Junlin;Lister, Derek;Uchida, Shunsuke;Liu, Lihui
    • Nuclear Engineering and Technology
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    • v.51 no.5
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    • pp.1345-1354
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    • 2019
  • Clogging of sump strainers that filter the recirculation water in containment after a loss-of-coolant accident (LOCA) seriously impedes the continued cooling of nuclear reactor cores. In experiments examining the corrosion of aluminium alloy 6061, a common material in containment equipment, in borated solutions simulating the water chemistry of sump water after a LOCA, we found that Fe-bearing intermetallic particles, which were initially buried in the Al matrix, were progressively exposed as corrosion continued. Their cathodic nature $vis-{\grave{a}}-vis$ the Al matrix provoked continuous trenching around them until they were finally released into the test solution. Such particles released from Al alloy components in a reactor containment after a LOCA will be transported to the sump entrance with the recirculation flow and trapped by the debris bed that typically forms on the strainer surface, potentially aggravating strainer clogging. These Fe-bearing intermetallic particles, many of which had a rod or thin strip-like geometry, were identified to be mainly the cubic phase ${\alpha}_c-Al(Fe,Mn)Si$ with an average size of about $2.15{\mu}m$; 11.5 g of particles with a volume of about $3.2cm^3$ would be released with the dissolution of every 1 kg 6061 aluminium alloy.

Evaluation of dissolution characteristics of magnetite in an inorganic acidic solution for the PHWR system decontamination

  • Ayantika Banerjee ;Wangkyu Choi ;Byung-Seon Choi ;Sangyoon Park;Seon-Byeong Kim
    • Nuclear Engineering and Technology
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    • v.55 no.5
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    • pp.1892-1900
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    • 2023
  • A protective oxide layer forms on the material surfaces of a Nuclear Power Plant during operation due to high temperature. These oxides can host radionuclides, the activated corrosion products of fission products, resulting in decommissioning workers' exposure. These deposited oxides are iron oxides such as Fe3O4, Fe2O3 and mixed ferrites such as nickel ferrites, chromium ferrites, and cobalt ferrites. Developing a new chemical decontamination technology for domestic CANDU-type reactors is challenging due to variations in oxide compositions from different structural materials in a Pressurized Water Reactor (PWR) system. The Korea Atomic Energy Research Institute (KAERI) has already developed a chemical decontamination process for PWRs called 'HyBRID' (Hydrazine-Based Reductive metal Ion Decontamination) that does not use organic acids or organic chelating agents at all. As the first step to developing a new chemical decontamination technology for the Pressurized Heavy Water Reactor (PHWR) system, we investigated magnetite dissolution behaviors in various HyBRID inorganic acidic solutions to assess their applicability to the PHWR reactor system, which forms a thicker oxide film.