• Title/Summary/Keyword: Single reactor

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A Study on the Characteristics of Flow with Polymer Additives (고분자물질 첨가에 의한 유동특성에 관한 연구)

  • 차경옥;김재근
    • Transactions of the Korean Society of Automotive Engineers
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    • v.4 no.3
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    • pp.176-186
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    • 1996
  • The phenomena of drag reduction using small quantities of a liner macromolecules has attracted the attention of many experimental investigations. On the other hand drag reduction in two phase flow can be applied to the transport of crude oil, phase change system such as chemical reactor, pool and boiling flow, and to flow with cavitation which occurs pump impellers. But the research on dragreduction in two phase flow is not sufficient. The purpose of the present work is to evaluate the drag reduction by measuring pressure drop, void fraction, mean liquid velocity and turbulent intensity whether polymer additives a horizontal single and two phase system or not. Flow pattern of air-water two phase flow was classified by electrical conductivity probe signal. Velocities and turbulent intensities of signal were measured simultaneously with a Hot-film anemometer.

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Design of Multistage Orifices for PIC System in Nuclear Reactor (원자로 압력 및 체적제어계통의 다단 오리피스 설계)

  • Shin, J.C.
    • Journal of Energy Engineering
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    • v.24 no.2
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    • pp.17-21
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    • 2015
  • Restriction orifices in the feed and bleed circuit of nuclear power plant are designed using computer program capable of handling multiple hole cascade orifice assembly. Single hole stages of orifice assembly are alternated with multihole stages where necessary. The distance between stages is such that it allows full pressure recovery. The minimum static pressure is higher than vapor pressure at the operating temperature so that cavitation does not occur. Piping sizes are reviewed and increased if necessary to improve rigidity.

Kinetics Prediction of Binary Aromatic Solvent Mixtures in Catalytic Oxidation Process (방향족 유기용매의 촉매산화공정에서 이성분계 혼합물의 속도특성 예측)

  • 이승범;윤용수;홍인권;이재동
    • Journal of environmental and Sanitary engineering
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    • v.16 no.1
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    • pp.66-71
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    • 2001
  • The objective of this study was to depict the kinetic behavior of the platinum catalyst for the deep oxidation of aromatic solvents and their binary mixtures. The oxidation kinetics of aromatic solvents, which were benzene, toluene and m-xylene, was studied on a 0.5% $Pt/{\gamma}-Al_2O_3$ catalyst. Deep oxidation of binary mixtures, which were 1:1 in volume, was carried out and the inlet concentration was controlled in the range of 133 and 333ppmv. An approach based on the two-stage redox model was used to analysis the results. The deep oxidation conversion of aromatic solvents was inversely proportional to inlet concentration in plug flow reactor. This trend is due to the zeroth-order kinetics with respect to inlet concentration. The kinetic parameters of multicomponent model were independently evaluated from the single compound oxidation experiments. A simple multicomponent model based on two-stage redox rate model made reasonably good predictions of conversion over the range of parameters studied.

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Multi Zone Fuel Model for CANDU Reactor (CANDU 원자로용 다영역 핵연료모델)

  • 전용준;오세기;정근모
    • Proceedings of the Korea Society for Energy Engineering kosee Conference
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    • 1993.11a
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    • pp.109-109
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    • 1993
  • CANDU 원자로 지역별 대표 핵연료봉 1개에 대하여 열행태를 해석할 수 있는 '평균 단일 핵연료(ASF : Averaged Single Fuel)' 모델을 우선 제안하였다. 핵 연료봉 하나를 12 개 동일 체적의 환형 격자로 나누고 시공간을 고려하는 전진 유한 미분 해석을 적용하여 핵연료봉내에서의 열적 변이를 모사 하였다. 핵연료의 전도도 및 비열은 온도에 종속함이 가정되었다. 주어진 열출력에 대하여, 핵연료와 피복관내의 정상상태 온도분포를 산출하였고 주어진 냉각재 온도 및 표면 열 전달 계수에 대하여 핵연료봉 단위 길이당 저장열을 계산하였다. 초기 온도 분포의 임의 값에 대하여, 시간 단계별 열출력 및 열전달 계수 변이에 따른 저장열, 온도 분포, 냉각재료의 출력과 피복관 온도 변이를 계산하였다. 이후 ASF 모델을 CANDU 14개 지역 출력 특성의 실제적 모사 및 해석이 가능하도록, 14개 지역 대표 핵연료봉모델 모두를 동시에 포함하는 '다영역 핵연료(MZF : Multi Zone Fuel)' 모델로 확장하였다.

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Evaluation of Distance Relay Operation Characteristic with the Reduction Devices Installed in Underground Power Cable Systems (시스순환전류 저감장치 설치시 거리계전기 응동 특성 평가)

  • Jung, Chae-Kyun;Lee, Jong-Beom;Kang, Ji-Won
    • Proceedings of the KIEE Conference
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    • 2003.07a
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    • pp.494-496
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    • 2003
  • This paper analyses the operation characteristic of distance relay when the single line to ground occurs in underground power cable systems that reduction device of sheath circulating current is installed. To apply that reduction device to actual system, the change of line impedance calculated at relay point is also analysed by the connection type of SVLs and fault location, fault inception angle with the installation of reduction device of reactor or not.

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VISUAL MEASUREMENT METHOD USING A CIRCULAR GROOVE IMAGE FOR MEASURING INTERNAL DEFECTS OF PIPES IN NUCLEAR POWER PLANT

  • Choi, Young-Soo;Jeong, Kyung-Min;Lee, Sung-Uk;Jung, Seung-Ho
    • Nuclear Engineering and Technology
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    • v.40 no.5
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    • pp.419-428
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    • 2008
  • During the overhaul period of nuclear power plants in Korea, an ROV(Remotely Operated Vehicle) enters the cold-leg pipes connected with the reactor to examine the state of the thermal sleeves and their positions in the safety injection nozzles. To measure the positions of the thermal sleeves or scratches with video images recorded during the examination, time-varying camera parameters should be known, such as the focal length and principal points used for the capturing each video image. In this paper, we propose a camera calibration and measurement scheme by using a single image containing two circular grooves of a cylindrical nozzle whose radius and distance are known.

Neutron Spectrum Effects on TRU Recycling in Pb-Bi Cooled Fast Reactor Core

  • Kim Yong Nam;Kim Jong Kyung;Park Won Seok
    • Nuclear Engineering and Technology
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    • v.35 no.4
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    • pp.336-346
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    • 2003
  • This study is intended to evaluate the dependency of TRU recycling characteristics on the neutron spectrum shift in a Pb-Bi cooled core. Considering two Pb-Bi cooled cores with the soft and the hard spectrum, respectively, various characteristics of the recycled core are carefully examined and compared with each other. Assuming very simplified fuel cycle management with the homogeneous and single region fuel loading, the burnup calculations are performed until the recycled core reached to the (quasi-) equilibrium state. The mechanism of TRU recycling toward the equilibrium is analyzed in terms of burnup reactivity and the isotopic compositions of TRU fuel. In the comparative analyses, the difference in the recycling behavior between the two cores is clarified. In addition, the basic safety characteristics of the recycled core are also discussed in terms of the Doppler coefficient, the coolant loss reactivity coefficient, and the effective delayed neutron fraction.

Effect of Radioisotope Position on Performance of Industrial SPECT (방사성동위원소 위치에 따른 산업용 SPECT 성능에 미치는 영향)

  • Moon, Jinho;Kim, Jongbum;Jung, Sung-Hee
    • Journal of Radiation Industry
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    • v.6 no.3
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    • pp.245-249
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    • 2012
  • Demand of fluid flow visualization has increased in industrial processes, because medical imaging technology is highly developed. As a part of the industrial process imaging technology, industrial single photon emission computed tomography (SPECT) system was developed to measure the cross-sectional distribution of the process fluid. The SPECT consists of 36 NaI (Tl) detectors with the hexagonal configuration. Reconstructed images were acquired for various positions of radioactive source to estimate SPECT device performance. To evaluate the reliability of the experimental results, the Monte Carlo simulation results are compared with experimental results. In general, the experimental and simulation results were consistent. However, as the source position was getting far from the center of the reactor, the accuracy of reconstructed images was compromised. It seems to be due to the inconsistent spatial resolution of the collimators according to the source position.

EXTENSION OF CFD CODES APPLICATION TO TWO-PHASE FLOW SAFETY PROBLEMS

  • Bestion, Dominique
    • Nuclear Engineering and Technology
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    • v.42 no.4
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    • pp.365-376
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    • 2010
  • This paper summarizes the results of a Writing Group on the Extension of CFD codes to two-phase flow safety problems, which was created by the Group for Analysis and Management of Accidents of the Nuclear Energy Agency' Committee on the Safety of Nuclear Installations (NEA-CSNI). Two-phase CFD used for safety investigations may predict small scale flow processes, which are not seen by system thermalhydraulic codes. However, the two-phase CFD models are not as mature as those in the single phase CFD and potential users need some guidance for proper application. In this paper, a classification of various modelling approaches is proposed. Then, a general multi-step methodology for using two-phase-CFD is explained, including a preliminary identification of flow processes, a model selection, and a verification and validation process. A list of 26 nuclear reactor safety issues that could benefit from investigations at the CFD scale is identified. Then, a few issues are analyzed in more detail, and a preliminary state-of-the-art is proposed and the remaining gaps in the existing approaches are identified. Finally, guidelines for users are proposed.

Comparing geometric parameters of a hydrodynamic cavitation process treating pesticide effluent

  • Randhavane, Shrikant B.
    • Environmental Engineering Research
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    • v.24 no.2
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    • pp.318-323
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    • 2019
  • Paper focuses on comparison between two different orifice plate configurations (plate number 1 and plate number 2) used as cavitating device in the hydrodynamic cavitation reactor for improving pollutant removal efficiencies. Effect of four different parameters such as hydraulic characteristics (in terms of range of flow rates, orifice velocities, cavitation number at different inlet pressures); cavitation number (in range of 5.76-0.35 for plate number 1 and 1.20-0.35 for plate number 2); inlet pressure (2-8 bars) and reaction time (0 to 60 min) in terms of chemical oxygen demand (COD) removal and chlorpyrifos degradation has been studied and compared. Optimum inlet pressure of 5 bars exists for degradation of pollutants for both the plates. It is found that geometry of orifice plate plays important role in removal efficiencies of pollutant. Results obtained confirmed that orifice plate 1 with configuration of 1.5 mm 17 holes; cavitational number of 1.54 performed better with around 60% COD and 98% chlorpyrifos removal as compared to orifice plate 2 having configuration of 2 mm single hole; cavitational number of 0.53 with 40% COD and 96% chlorpyrifos in 2 h duration time.