• Title/Summary/Keyword: Reactor Parameter

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Characteristics of Glucose Oxidase Reaction of Onion Juice (양파 착즙액과 포도당 산화효소의 반응 특성)

  • Choi, Bong-Young;Lee, Eun-Mi;Kim, Young-Ran;Kim, Hyun-Jong;Chung, Bong-Woo
    • Korean Journal of Food Science and Technology
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    • v.35 no.3
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    • pp.417-422
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    • 2003
  • The onions are considered to be a favorable functional source of beverage because they contain much sugar and various nutrients, and they are juicy vegetable. Recently, consumers have a new trend to take functional foods with health benefits. To meet this need, this study was the basic research to establish a manufacturing process of functional onion beverage by glucose oxidase. Glucose oxidase catalyzes reaction of glucose oxidation and makes generation of gluconic acid. Kinetics of the reaction was also investigated, and maximum glucose consumption rate $(V_{max})$ of $26.1{\times}10^{-2}\;g/L{\cdot}min$ and $K_m$ of 5.84 g/L were obtained. Optimum conditions were obtained when the glucose oxidase catalyzed reaction was carried out at temperature of $25^{\circ}C$, agitation rate of 450 rpm and aeration rate of 4 vvm in a 2.5 L jar fermentor. Finally, the enzyme reactor was 10-times scaled up and a similar glucose oxidation performance was achieved in the scaled-up reactor.

Reaction Rate Analysis of Combustion for Indonesian Coal Char Applied by External/Internal Diffusion (외부 및 내부 확산을 적용한 인도네시아 석탄촤의 연소 반응율 분석)

  • Hwang, Chan-Won;Kim, Ryang-Gyoon;Ryu, Kwang-Il;Wu, Ze-Lin;Jeon, Chung-Hwan
    • Korean Chemical Engineering Research
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    • v.52 no.1
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    • pp.133-140
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    • 2014
  • The experiment was designed to compare the char combustion kinetics of pulverized Indonesia coals commonly utilized in Korea power plants. The reaction rate of coal char has been formulated using the external and internal effectiveness factors to describe the diffusion effect quantitatively. The Random Pore Model (RPM) was used for applying internal specific surface area as a function of carbon conversion ratio. Reaction rate was obtained from reaction time using the Wire Heating Reactor (WHR) which can heat and measure the char particle temperature at the same time. BET and TGA were used to obtain physical properties such as internal specific surface area and structural parameter. Three kinds of Indonesia Sub-bituminous coals "BARAMULTI, ENERGYMAN, AGM" were used in order to derive the activation energy and pre-exponential factor. The results of this study showed that the effect of internal diffusion than that of external diffusion is the dominant as comparison of kinetics was reflected in external and internal effectiveness factors. For three kinds of coal char, finally, activation energy of intrinsic kinetics indicates 110~118 kJ/mol.

Heat transfer analysis in sub-channels of rod bundle geometry with supercritical water

  • Shitsi, Edward;Debrah, Seth Kofi;Chabi, Silas;Arthur, Emmanuel Maurice;Baidoo, Isaac Kwasi
    • Nuclear Engineering and Technology
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    • v.54 no.3
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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.

Performance Experiments and Analysis of Nonlinear Behavior for HDRB using in Seismic Isolation (면진용 고감쇠 적층고무베어링의 성능 특성 실험 및 비선형 거동해석)

  • Koo, Gyeong-Hoi;Lee, Jae-Han;Yoo, Bong
    • Journal of the Earthquake Engineering Society of Korea
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    • v.2 no.4
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    • pp.73-86
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    • 1998
  • The purpose of this paper is to evaluate the shear stiffness, hysteretic behavior, and ultimate behavior of HDRB(High Damping Rubber Bearing), which will be included in the seismic isolation design guideline as requirements. To do this, two 1/8 scaled HDRB are designed, fabricated, and tested to show the mechanical characteristics. The shear stiffness obtained from the proposed equation of the shear stiffness shows a good agreement with those of the experiments. For analysis of the hysteretic behavior of HDRB using the modified rate model, the parameter equations are obtained from the experiments. Using the obtained parameter equations for the modified rate model, the seismic response analyses are carried out for 1-D system. The results of analysis well follow the hysteretic behavior of HDRB obtained from the experiments. To evaluate the ultimate behavior of HDRB used in this paper, the analyses are carried out using the modified macro model, which can consider the large shear deflection. The critical shear strain(CSS) is defined to express the maximum allowable shear strain and vertical load. From the analyses, the CSS, showing the instability, decreases significantly as increased the vertical loads. The CSS is not appeared for the design vertical load in the used HDRB. In analysis using about 5 times of design vertical load, the HDRB start to show the instability transient and for about 7 times, the CSS is about 350%.

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Correlation Between Transient Regime and Steady-State Regime on Creep Crack Growth Behavior of Grade 91 Steel (Grade 91 강의 크리프 균열성장 거동에 대한 천이영역과 정상상태영역의 상관 관계)

  • Park, Jae-Young;Kim, Woo-Gon;Ekaputra, I.M.W.;Kim, Seon-Jin;Kim, Eung-Seon
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.39 no.12
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    • pp.1257-1263
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    • 2015
  • A correlation between the transient regime and steady state regime on the creep crack growth (CCG) for Grade 91 steel, which is used as the structural material for the Gen-IV reactor systems, was investigated. A series of CCG tests were performed using 1/2" CT specimens under a constant applied load and at a constant temperature of $600^{\circ}C$. The CCG rates for the transient and steady state regimes were obtained in terms of $C^*$ parameter. The transient CCG rate had a close correlation with the steady-state CCG rate, as the slope of the transient CCG data was very similar to that of the steady state data. The transient rate was slower by 5.6 times as compared to the steady state rate. It can be inferred that the steady state CCG rate, which is required for long-time tests, can be predicted from the transient CCG rate obtained from short-time tests.

Study on the Steam Line Break Accident for Kori Unit-1 (고리 1호기에 대한 증기배관 파열사고 연구)

  • Tae Woon Kim;Jung In Choi;Un Chul Lee;Ki In Han
    • Nuclear Engineering and Technology
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    • v.14 no.4
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    • pp.186-195
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    • 1982
  • The steam line break accident for Kori Unit 1 is analyzed by a code SYSRAN which calculates nuclear power and heat flux using the point kinetics equation and the lumped-parameter model and calculates system transient using the mass and energy balance equation with the assumption of uniform reactor coolant system pressure. The 1.4 f $t^2$ steam line break accident is analyzed at EOL (End of Life), hot shutdown condition in which case the accident would be most severe. The steam discharge rate is assumed to follow the Moody critical flow model. The results reveal the peak heat flux of 38% of nominal full power value at 60 second after the accident initiates, which is higher than the FSAR result of 26%. Trends for the transient are in good agreement with FSAR results. A sensitivity study shows that this accident is most sensitive to the moderator density coefficient and the lower plenum mixing factor. The DNBR calculation under the assumption of $F_{{\Delta}H}$=3.66, which is used in the FSAR with all the control and the shutdown assemblies inserted except one B bank assembly and of Fz=1.55 shows that minimum DNBR reaches 1.62 at 60 second, indicating that the fuel failure is not anticipated to occur. The point kinetics equation, the lumped-parameter model and the system transient model which uses the mass and energy balance equation are verified to be effective to follow the system transient phenomena of the nuclear power plants.lear power plants.

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Development of Liquid Metal Passive Cooling Flow Simulation System (액체금속 피동냉각유동모사 실증설비의 개발)

  • Ryu, Kyung-Ha;Kim, Jae-Hyoung;Lee, Tae-Hyun;Lee, Sang-Hyuk;Bahn, Byoung-Min
    • Transactions of the KSME C: Technology and Education
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    • v.3 no.4
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    • pp.257-264
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    • 2015
  • To maintain sustainability of nuclear energy as an important energy source, both safety problem and Spent Nuclear Fuels(SNFs) problem should be solved. In case of Gen-IV reactors such as fast reactor, SNFs can be used as fuels by using fast neutrons. It can be a suitable treatment method of high-level waste in near future. Liquid metals such as Sodium or Lead-Bismuth Eutectic (LBE) can be possibly used as a coolant to use fast neutrons. In this paper, it was described that natural circulation parameter studies, design analyses, material selections and a completion of facilities. To develop a natural circulation facility, thermal hydraulic analyses were performed. Installation technique of liquid metal natural circulation were secured.

A Study of Ozonation Characteristics of Bis(2-chloroethyl) Ether (Bis(2-chloroethyl) Ether (BCEE)의 오존산화 특성에 관한 연구)

  • Lee, Cheal-Gyu;Kim, Moon-Chan
    • Applied Chemistry for Engineering
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    • v.21 no.6
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    • pp.610-615
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    • 2010
  • In this study ozonation of bis(2-chloroethyl) ether (BCEE) in aqueous solution was performed in a laboratory scale batch reacter. The ozonation process of BCEE was carried out by bubbling ozone at the bottom of reactor containing the BCEE solution. Ozonation was almost complete after 80 min with an ozone concentration of $50{\pm}10mg/L$. Ozonation treatment efficiencies of BCEE were evaluated in terms of $BOD_5$, $COD_{Cr}$, and TOC. In the ozonation of BCEE a 62.79% decrease of the $COD_{Cr}$ and a 57.25% decrease of the TOC lead to biodegradable by-products ($BOD_5/COD_{Cr}$ = 0.39). The results of this research show that wastewaters containing non-biodegradable compounds, such as BCEE can be successfully treated by ozonation followed by bio-treatment. The pseudo first-order rate constants of the ozonation was $2.00{\times}10^{-4}sec^{-1}$ and the activation energy was $10.02kcal{\cdot}mol^{-1}$ at $30^{\circ}C$.

Experimental Study on Hydrogen Direct Reduction of Hematite in a Lab Scale Fluidized Bed Reactor by Estimating the Gas Consumption Rate

  • Hasolli, Naim;Jeon, Seong Min;Park, Young Ok;Kim, Yong Ha
    • Clean Technology
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    • v.21 no.2
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    • pp.96-101
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    • 2015
  • Hematite reduction using hydrogen was conducted and the various process parameters were closely observed. A lab scale fluidized bed unit was designed especially for this study. The optimal values of the gas velocity, reduction time and temperature were evaluated. The values which indicated the highest reduction rate were set as fixed parameters for the following tests starting with the reduction time of 30 minutes and 750 ℃ of temperature. Among these variables the one with the highest interest was the gas specific consumption. It will tell the amount of the gas which is required to achieve a reduction rate of over 90% at the optimal conditions. This parameter is important for the scale up of the lab scale unit. 1,500 Nm3/ton-ore was found to be the optimal specific gas consumption rate at which the reduction rates exhibit the highest values for hematite.

A Study on Loose Part Monitoring System in Nuclear Power Plant Based on Neural Network (원전 금속파편시스템에 신경회로망 적용연구)

  • Kim, Jung-Soo;Hwang, In-Koo;Kim, Jung-Tak;Moon, Byung-Soo;Lyou, Joon
    • Proceedings of the Korean Institute of Intelligent Systems Conference
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    • 2002.05a
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    • pp.227-230
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    • 2002
  • The Loose Part Monitoring System(LPMS) has been designed to detect, locate and evaluate detached or loosened parts and foreign objects in the reactor coolant system. In this paper, at first, we presents an application of the back propagation neural network. At the preprocessing step, the moving window average filter is adopted to reject the low frequency background noise components. And then, extracting the acoustic signature such as Starting point of impact signal, Rising time, Half period, and Global time, they are used as the inputs to neural network. Secondly, we applied the neural network algorithm to LPMS in order to estimate the mass of loose parts. We trained the impact test data of YGN3 using the backpropagation method. The input parameter for training is Rising Time, Half Period, Maximum amplitude. The result showed that the neural network would be applied to LPMS. Also, applying the neural network to the Practical false alarm data during startup and impact test signal at nuclear power Plant, the false alarms are reduced effectively. 1.

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