• Title/Summary/Keyword: Combination reactor

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Effects of Initial Concentration and Nutrients in Treatment of petroleum Hydrocarbon Contaminated Soils using a Slurry-Phase Bioreactor (슬러리상 생물반응기를 이용한 석유계탄화수소 오염토양의 처리에 있어서 초기농도 및 영양소의 영향)

  • 김수철;남궁완;박대원
    • Journal of Korea Soil Environment Society
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    • v.3 no.3
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    • pp.45-53
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    • 1998
  • The purpose of this study was to evaluate effects of initial concentration and nutrients in treatment of petroleum hydrocarbon contaminated soils. The reactor used in this study was slurry-phase bioreactor of in-vessel type. Performance results on treatment of diesel fuel contaminated soils and micorbial growth were generated at the bench-scale level. The fate of TPH(Total Petroleum Hydrocarbon) and the microbial growth were evaluated in combination with biodegradation rate. Effect of initial loading levels of 50,000 and 100,000mg TPH/kg soil was studied. Performance results with two reactors were showed at the total TPH removal rate of 90.5% and 90.8%, respectively. However, the reactor with the initial concentration of 50,000mg TPH/kg soil showed higher biological TPH removal efficiency except for removal by volatilization than the other Although the different amount of nutrients was applied in two reactors, there was no remarkable difference in microbial growth rate. However, considerable factor in this results was that applied different initial concentration to two reactors. Although initial concentration was two times higher than it applied to the reactor without addition of nutrients, in total and biological TPH removal rate the reactor with addition of nutrients showed a higher than the other.

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Nuclear Design Analysis of Wolsung-1 CANDU-PHW Nuclear Generating Station

  • Chung, Chang-Hyun;Oh, Keun-Bae;Kim, C.H.
    • Nuclear Engineering and Technology
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    • v.10 no.4
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    • pp.203-213
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    • 1978
  • A combination of computer codes such as LATREP, HWR, AXAV and CITATION is utilized in an attempt to analyze the nuclear design characteristics of the CANDU-PHWR of the Wolsung Unit 1. The major nuclear properties to be computed are tile lattice properties of CANDU fuel channel and the core channel power distribution. The computed results are compared with the PSR documentation for the Wolsung reactor. The observed discrepancies between our computation and the PSB values are discussed in terms of incomplete information on the description of the core configuration in the PSR and the different calculation methods.

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Photocatalytic Degradation of Algae and its By-product using Rotating Photocatalytic Oxidation Disk Reactor

  • Son, Hee-Jong;Jung, Chul-Woo;Bae, Sang-Dae
    • Environmental Engineering Research
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    • v.14 no.3
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    • pp.170-173
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    • 2009
  • This study examined the special technique of photocatalytic degradation (RPODisk) for removal of taste and odor causing materials, algae, and algal toxin. The RPODisk was effective for removal of these troublesome contaminants. It outperformed the fixed media and the UV irradiation for geosmin removal. The RPODisk performance was comparable to the combination of the UV irradiation with TiO2. The RPODisk performance was affected by the rotating speed. The faster the speed was, the better the performance. The RPODisk was also effective for removal of algae and algal toxin. The algal activity reduced by 80% after 30 mins of the treatment. More toxic microcystin (MC)-LR was more difficult to remove than MC-RR. The times for 50% removal were 23.7 mins for MC-LR and 14.1 mins for MC-RR. Almost 100 mins of the contact time was required to completely remove MC-LR at the rotating speed of 260 rpm.

A Study on the Analysis of Failures Related to Emergency Diesel Generators in Overseas Nuclear Power Plants (원전용 비상디젤발전기 국외 손상사례 분석에 관한 연구)

  • Chang, Jung-Hwan;Kim, Jin-Sung;Chung, Hae-Dong;Cho, Kwon-Hae
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.5 no.1
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    • pp.32-37
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    • 2009
  • The emergency diesel generator (EDG) in a nuclear power plant (NPP) shall start within 10 secondss and supply electrical power to engineered safety features within one minute and less if a loss of offsite power (LOOP), A design-basis event, or their combination occur. Each NPP has an EDG set consisting of two diesel generators for redundancy. In addition to the EDG set, an alternate Alternating Current Diesel Generator (AAC DG) is installed and shared by several units to cope with a station black out (SBO), i.e., loss of the offsite power concurrent with reactor trip and unavailability of the EDG set. The objective of this study is to analyze the failure data of emergency diesel generators reported in overseas nuclear power plants.

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Dynamics of Microbial Community of Aerobic Biofilm Reactor using Rhodococcus sp. EL-GT and Activated Sludge for Phenol Wastewater Treatment (페놀폐수 처리를 위한 Rhodococcus sp. EL-GT와 활성슬러지를 이용한 호기성 생물막 반응기의 미생물 군집 동태)

  • 박근태;원성내;손홍주;남귀숙;이재동;이상준
    • Journal of Environmental Science International
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    • v.10 no.3
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    • pp.239-245
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    • 2001
  • This research was performed to investigate the dynamics of microbial community by RBC (Rotating Biological Contactor) using Rhodococcus sp. EL-GT and activated sludge. Cell counts revealed by DAPI were compared with culturable bacterial counts from nutrient agar. Colony counts on nutrient agar gave values 20~25% and 1~15% of cell counts (DAPI). The cell counts for the dynamics of bacterial community were determined by combination of in situ hybridization with fluorescently-labelled oligonyucleotide probes and epifluorescence microscopy. Around 90~80% of total cells visualized DAPI were also detected by the bacteria probe EUB 338. For both reactors proteobacteria belonging to the gamma subclass were dominant in the first stage (1 and 2 stage) and proteobacteria belonging to the gamma subclass were dominant in the last stage (3 and 4 stage).

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Parallel Multiple Electric Power Conversion System Constructed by Connecting Three Power Converters

  • Nakai, Mitsuki;Inaba, Hiromi;Kishine, Keiji;Ishikura, Keisuke
    • Journal of international Conference on Electrical Machines and Systems
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    • v.3 no.3
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    • pp.276-281
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    • 2014
  • The electric power conversion system constructed by connecting two or more power converters in parallel is an advantageous method for making to large capacity and standardization. In this paper, the control method of cross current when three power converters are operated is examined, and it reexamined a preferable system construction method.

Optimization of a Wire-Spacer Fuel Assembly of Liquid Metal reactor

  • Ahmad, Imteyaz;Kim, Kwang-Yong
    • 유체기계공업학회:학술대회논문집
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    • 2005.12a
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    • pp.240-243
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    • 2005
  • This study deals with the shape optimization of a wire spacer fuel assembly of Liquid Metal Reactors (LMRs). The Response Surface based optimization Method is used as an optimization technique with the Reynolds-averaged Navier-Stokes analysis of fluid flow and heat transfer using Shear Stress Transport (SST) turbulence model as a turbulence closure. Two design variables namely, pitch to fuel rod diameter ratio and lead length to fuel rod diameter ratio are selected. The objective function is defined as a combination of the heat transfer rate and the inverse of friction loss with a weighting factor. Three level full-factorial method is used to determine the training points. In total, nine experiments have been performed numerically and the resulting datas have been analysed for optimization study. Also, a comparison has been made between the optimized surface and the reference one in this study.

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Simulation of a Dually Excited Capacitively Coupled RF Plasma

  • Kim, Heon-Chang;Sul, Yong-Tae;Park, Sung-Jin
    • 한국정보디스플레이학회:학술대회논문집
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    • 2005.07a
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    • pp.513-514
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    • 2005
  • In plasma processing reactors, it is common practice to control plasma density and ion bombardment energy by manipulating excitation voltage and frequency. In this paper, a dually excited capacitively coupled rf plasma reactor is self-consistently simulated with a three moment model. Effects of phase differences between primary and secondary voltage waves, simultaneously modulated at various combination of commensurate frequencies, on plasma properties are investigated. The simulation results show that plasma potential and density as well as primary self-dc bias are nearly unaffected by the phase lag between the primary and the secondary voltage waves. The results also show that, with the secondary frequency substantially lower than the primary frequency, secondary self-dc bias remains constant regardless of the phase lag. As the secondary frequency approaches to the primary frequency, however, the secondary self-dc bias becomes greatly altered by the phase lag, and so does the ion bombardment energy at the secondary electrode. These results demonstrate that ion bombardment energy can be more carefully controlled through plasma simulation.

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A review of fatigue failures in LWR plants in Japan

  • Kunihiro, Iida
    • Proceedings of the KWS Conference
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    • 1996.10a
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    • pp.19-34
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    • 1996
  • A review was made of fatigue failures of nuclear power plant components in Japan, which were experienced in service and during periodical inspection. No case has been recently reported of a service fatigue failure of a reactor pressure vessel itself, excluding nozzle corner cracks, that occurred many years ago. But, service fatigue failures have been occasionally experienced in piping systems, pumps, and valves, on which fatigue design seems to have been inadequately applied. The causes of fatigue failures can be divided into two categories: mechanical-vibration-induced fatigue and thermal-fluctuation-induced fatigue. Vibration-induced fatigue failure occurs more frequently than is generally thought. The lesson gleaned from the present survey is a recognition that a service fatigue failure may occur due to any one or a combination of the following factors: (1) lack of communication between designers and fabrication engineers, (2) lack of knowledge about a possibility of fatigue failure and poor consideration about the effects of residual stresses, (3) lack of consideration on possible vibration in the design and fabrication stages, and (4) lack of fusion or poor penetration in a welded joint.

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Shape Optimization of A Twist Mixing Vane in Nuclear Fuel Assembly (핵연료 봉다발내 비틀린 혼합날개의 형상최적설계)

  • Jung, Sang-Ho;Kim, Kwang-Yong
    • The KSFM Journal of Fluid Machinery
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    • v.12 no.4
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    • pp.7-13
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    • 2009
  • The purposes of present work are to analyze the convective heat transfer with three-dimensional Reynolds-averaged Navier-Stokes analysis, and to optimize shape of the mixing vane using the analysis results. Response surface method is employed as an optimization technique. The objective function is defined as a combination of inverse of heat transfer rate and friction loss. Two bend angles of mixing vane are selected as design variables. Thermal-hydraulic performances have been discussed and optimum shape has been obtained as a function of weighting factor in the objective function. The results show that the optimized geometry improves the heat transfer performance far downstream of the mixing vane.