• Title/Summary/Keyword: Reactor

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Effects of the Redox Potential of the Acidogenic Reactor on the Performance of a Two-Stage Methanogenic Reactor

  • Phae, Chae-Gun;Lee, Wan-Kyu;Kim, Byung-Hong;Koh, Jong-Ho;Kim, Sang-Won
    • Journal of Microbiology and Biotechnology
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    • v.6 no.1
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    • pp.30-35
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    • 1996
  • Distillery wastewater was used in a thermophilic laboratory-scale two stage anaerobic digester to test the effects of the redox potential of the first acidogenic reactor on the performance of the system. The digester consisted of first a acidogenic reactor and the an upflow anaerobic sludge blanket (UASB) reactor. The digestor was operated at a hydraulic retention time (HRT) of 48 h. Under these conditions, about 90% of the chemical oxygen demand as measured by the chromate method ($COD_{cr}$) was removed with a gas production yield of 0.4 l/g-COD removed. The redox potential of the acidogenic reactor was increased when the reactor was purged with nitrogen gas or agitation speed was increased. The increase in reduction potential was accompanied by an increase in acetate production and a decrease in butyrate formation. A similar trend was observed when a small amount of air was introduced into the acidogenic reactor. It is believed that the hydrogen partial pressure in the acidogenic reactor was decreased by the above mentioned treatments. The possible failure of anaerobic digestion processes due to over-loading could be avoided by the above mentioned treatments.

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A Study on the Mixed-Food Wastewater Treatment in an Anaerobic Packed Bed Reactor and Sludge Bed Reactor (혐기성 고정상반응기와 슬러지 Bed반응기에서 혼합-식품폐수처리에 관한 연구)

  • 안재동;김재우;장인용
    • Journal of Environmental Health Sciences
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    • v.19 no.4
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    • pp.38-43
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    • 1993
  • The characteristics of food wastewater treatment in an anaerobic packed bed reactor (APBR) with polyurethane as a packing material and sludge bed reactor (ASBR) was studied. The reactor of 9cm-ID, 150cm-height was fed in a continuous mode from bottom of reactor. For the purpose of constant temperature of reactor, water jacket was installed. The used packing materials was polyurethane sponge foam. Methane which was produced by decomposed organics collected at the top of the reactor for using as a fuel. The substrates used were synthetic, mixed and food wastewater. For the acclimatization of microorganisms, mixed wastewater was used. The major analyses were gas production, COD, pH and volatile acids. Based upon the completed works, the results are as follows: When food wastewater was fed the quantity of produced gas was less than that of synthetic wastewater, but food process saw higher methane content than synthetic process. As well as COD removal efficiency of food process reached at about 85%. In aspect of effluent volatile acid, food process showed low concentration of below 500 mg/l, therefore anaerobic reaction stabled. Conclusively food wastewater used can be digested by anaerobic treatment, especially anaerobic packed bed reactor showed 82% of COD removal, 75% of methane content, 10 l of gas production, and anaerobic sludge bed reactor did 79% of COD removal, 75% of methane content, 81 of gas production at 4 kgCOD/m$^3$day, 36$\circ$C.

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Development and validation of reactor nuclear design code CORCA-3D

  • An, Ping;Ma, Yongqiang;Xiao, Peng;Guo, Fengchen;Lu, Wei;Chai, Xiaoming
    • Nuclear Engineering and Technology
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    • v.51 no.7
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    • pp.1721-1728
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    • 2019
  • The advanced node core code CORCA-3D is one of the independent developed codes of NPIC for the nuclear reactor core design. CORCA-3D code can calculate the few-group cross section, solve the 3D diffusion equations, consider the thermal-hydraulic feedback, reconstruct the pin-by-pin power. It has lots of functions such as changing core status calculation, critical searching, control rod value calculation, coefficient calculation and so on. The main theory and functions of CORCA-3D code are introduced and validated with a lot of reactor measured data and the SCIENCE system. Now, CORCA-3D code has been applied in ACP type reactor nuclear cores design.

Influencing Parameters on Supercritical Water Reactor Design for Phenol Oxidation

  • Akbari, Maryam;Nazaripour, Morteza;Bazargan, Alireza;Bazargan, Majid
    • Korean Chemical Engineering Research
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    • v.59 no.1
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    • pp.85-93
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    • 2021
  • For accurate and reliable process design for phenol oxidation in a plug flow reactor with supercritical water, modeling can be very insightful. Here, the velocity and density distribution along the reactor have been predicted by a numerical model and variations of temperature and phenol mass fraction are calculated under various flow conditions. The numerical model shows that as we proceed along the length of the reactor the temperature falls from above 430 ℃ to approximately 380 ℃. This is because the generated heat from the exothermic reaction is less that the amount lost through the walls of the reactor. Also, along the length, the linear velocity falls to less than one-third of the initial value while the density more than doubles. This is due to the fall in temperature which results in higher density which in turn demands a lower velocity to satisfy the continuity equation. Having a higher oxygen concentration at the reactor inlet leads to much faster phenol destruction; this leads to lower capital costs (shorter reactor will be required); however, the operational expenditures will increase for supplying the needed oxygen. The phenol destruction depends heavily on the kinetic parameters and can be as high as 99.9%. Using different kinetic parameters is shown to significantly influence the predicted distributions inside the reactor and final phenol conversion. These results demonstrate the importance of selecting kinetic parameters carefully particularly when these predictions are used for reactor design.

Conceptual designs and characteristic of the fuel handling and transfer system for 150 MWe PGSFR and 1400 MWe SFR burner reactor

  • Kang-Soo Kim;Jong-Bum Kim;Chang-Gyu Park
    • Nuclear Engineering and Technology
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    • v.54 no.11
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    • pp.4125-4133
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    • 2022
  • KAERI (Korea Atomic Energy Research Institute) developed the conceptual design of PGSFR (Prototype Gen-IV Sodium Cooled Fast Reactor) and Burner Reactor. Since the reactor characteristics of the PGSFR and Burner Reactor are different, the shape, size and the arrangement of the main components in the reactors must be different. Therefore, the conceptual design for the fuel handling and transfer systems needs to be performed coinciding with the structure of the reactor. Especially, because a redan structure dividing hot and cold pool is installed in the reactor vessel, the conceptual design of the fuel handling and transfer system largely changes depending on the location of the redan structure. Various elements of the conceptual design and an integral arrangement for the fuel handling and transfer system were arranged according to the characteristics, sizes and shapes of the reactors. In this paper, the conceptual designs of the fuel handling and transfer system for PGSFR and Burner Reactor are described. Especially, an A-frame method is selected as the fuel handling and transfer system for the Burner Reactor, considering the layout of the internal structure. The tilt angle, diameter and length of A-frame is determined and the strength evaluation of the A-frame is performed.

Online training and education from the VR-1 reactor-Lessons learned

  • Ondrej Novak;Tomas Bily;Ondrej Huml;Lubomir Sklenka;Filip Fejt;Jan Rataj
    • Nuclear Engineering and Technology
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    • v.55 no.12
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    • pp.4465-4471
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    • 2023
  • Hands-on education and training is a key part of fixing and developing technology knowledge and is an inherent part of many engineering and scientific curricula. However, access to large complex training facilities, such as nuclear reactor, could be limited by various factors, such as unavailability of those facilities in the region, high traveling costs or harmonization of the schedules of hands-on E&T with theoretical lectures and with the operational schedule of the facility. To handle the issue, several success stories have been reached with the introduction of the Internet Reactor Labs (IRL). The Internet Reactor Labs can strongly contribute to accessibility of training at research reactors and can contribute to improvements in their utilization. The paper describes the development of the Internet Reactor Lab at the VR-1 reactor of the Czech Technical University in Prague. Contrary to single-purpose IRLs, it presents various modalities of online teaching and training in experimental reactor physics and reactor operation in general as well as outreach activities that have been developed in recent years.

Nanoliter Reactor Arrays for Antibiotic Study

  • Park, Jin-Won
    • Bulletin of the Korean Chemical Society
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    • v.28 no.10
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    • pp.1709-1714
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    • 2007
  • It is demonstrated in this study that the nanoliter reactor arrays with an inkjet printing, can be used for high throughput screen of antibiotic function. As a model antibiotic, gramicidin was used in this study. The gramicidin embedded lipid vesicles were immobilized on the surface in the nanoliter reactor structure with control of the volume in the nanoliter reactor. By dispensing acidic drops into the reactor, the gramicidin function was monitored. The technique developed in this research also has a great potential to be used for discovery of drugs.

A Numerical Study on Pyrolysis of Trichloroethane for Reactor geometry design (TCE 열분해 반응기의 형상 설계를 위한 수치해석적 연구)

  • La, Seung-Hyuck;Kang, Kyung-Tae;Kim, Sang-Young;Hwang, Jung-Ho
    • 한국연소학회:학술대회논문집
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    • 2002.06a
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    • pp.106-110
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    • 2002
  • Trichlorethane (TCE) is known as one of major carcinogens. TCE is difficult to be incinerated environmentally friendly, so pyrolysis is suggested for TCE treatment. In this study, we examined effects of cylinder-type pyrolysis reactor design parameters like existence of baffle inside reactor and reactor operating condition like heating reactor wall temperature and residence time numerically using CFX 4.3, a commercial computational fluid dynamic program.

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Optimization of a semi-batch esterification reactor (반회분 에스테르화 반응기의 최적화)

  • 이융효;박선원
    • 제어로봇시스템학회:학술대회논문집
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    • 1993.10a
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    • pp.582-588
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    • 1993
  • A scheme of dynamic optimization for batch reactor his been developed and applied to a semi-batch esterification reactor. To obtain optimal operating conditions for the given semi-batch reactor system with complex reaction kinetic and process constraints, a general nonlinear programming solver and finite element techniques have been introduced. The optimization results for the complex reactor system have been compared with those of Kumar et al. [1984] to show better optimization performance. The proposed optimizing scheme has been applied to the free end time problem to obtain the realistic operating condition. The results can supply valuable information for economic operation of the given batch esterification reactor.

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Detection of Antineutrinos for Reactor Monitoring

  • Kim, Yeongduk
    • Nuclear Engineering and Technology
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    • v.48 no.2
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    • pp.285-292
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    • 2016
  • Reactor neutrinos have been detected in the past 50 years by various detectors for different purposes. Beginning in the 1980s, neutrino physicists have tried to use neutrinos to monitor reactors and develop an optimized detector for nuclear safeguards. Recently, motivated by neutrino oscillation physics, the technology and scale of reactor neutrino detection have progressed considerably. In this review, I will give an overview of the detection technology for reactor neutrinos, and describe the issues related to further improvements in optimized detectors for reactor monitoring.