• 제목/요약/키워드: wall decay

검색결과 96건 처리시간 0.024초

레이저 형광여기법(LIF)를 이용한 복잡 난류유동장의 혼합특성에 관한 연구 (A Study on the Mixing Characteristics in Complex Turbulent Flow by a Laser Induced Fluorescence Method)

  • 김경천;정은호
    • 대한기계학회:학술대회논문집
    • /
    • 대한기계학회 2001년도 춘계학술대회논문집E
    • /
    • pp.542-547
    • /
    • 2001
  • A non-intrusive Planar Laser-Induced Fluorescence(PLIF) technique was applied to study the turbulent mixing process in a Rushton turbine reactor. Instantaneous and ensemble averaged concentration fields are obtained by measuring the fluorescence intensity of Rhodamine B tracer excited by a thin Nd:Yag laser sheet illuminating the whole center plane of the stirred tank. The gray level images captured by a 14-bit cooled CCD camera can be transformed to the local concentration values using a calibration matrix. The dye injection point was selected at the tank wall with three quarter height (3/4H) from the tank bottom to observe the mixing characteristics in upper bulk flow region. There exist distinct two time scales: the rapid decay of mean concentration in each region after the dye infusion reflects the large scale mixing while the followed slow decay reveals the small scale mixing. The temporal change of concentration probability functions conjectures the two sequential processes in the batch type mixing. An inactive column of water existed above the impeller disk, in which the fluid rotates with the shaft but is isolated from the mean bulk flow.

  • PDF

레이저 형광여기법(LIF)를 이용한 러쉬톤 터빈 교반기의 혼합특성에 관한 연구 (A Study on the Mixing Characteristics in a Rushton Turbine Reactor by a Laser Induced Fluorescence Method)

  • 정은호;김경천
    • 대한기계학회논문집B
    • /
    • 제26권8호
    • /
    • pp.1145-1152
    • /
    • 2002
  • A non-intrusive Planar Laser-Induced Fluorescence(PLIF) technique was applied to study the turbulent mixing process in a Rushton turbine reactor. Instantaneous and ensemble averaged concentration fields was obtained by measuring the fluorescence intensity of Rhodamine B tracer excited by a thin Nd:Yag laser sheet illuminating the whole center plane of the stirred tank. The gray level images captured by a 14-bit cooled CCD camera could be transformed to the local concentration values using a calibration matrix. The dye injection point was selected at the tank wall with three quarter. height (3/4H) from the tank bottom to observe the mixing characteristics in upper bulk flow region. There exist distinct two time scales: the rapid decay of mean concentration after the dye infusion reflects the large scale turbulent mixing while the fellowed slow decay reveals the small scale molecular mixing. The temporal change of concentration variance field conjectures the two sequential processes for the batch type mixing. An inactive column of water is existed above the impeller disk, in which the fluid rotates with the shaft but is isolated from the mean bulk flow.

Neutral Loop Discharge 플라즈마의 전자거동과 최적조건에 관한 기초적 연구 (A Fundamental Study on the Electron Behavior and Optimum Condition for the Formation of a Neutral Loop Discharge Plasma)

  • 성열문;김종경;박정후
    • 대한전기학회논문지:전기물성ㆍ응용부문C
    • /
    • 제50권6호
    • /
    • pp.281-287
    • /
    • 2001
  • In order to obtain guidelines for design and operation of a new plasma source by a magnetic neutral loop discharge(NLD), the electron behavior was studied experimentally and numerically. Experimentally, the magnetic field gradient was changed over a wide range, and it was found that there existed an optimum value for efficient plasma production. Analyses of the electron behavior were performed using a model that included effects of a three dimensional electromagnetic field configuration considering the spatial decay of the electric field, and the limitation to the motion of electron caused by the existence of walls and thus electron loss at wall surfaces. These three dimensional factors were found to explain the existence of the optimum magnetic field gradient. It was shown that the L dependence of the plasma production efficiency was firstly decided by the finite decay length of the electric field strength, which was further modified by electron elastic collisions with neutral atoms which drove the electron to walls. The latter effect tends to reduce the optimum value of L.

  • PDF

수직냉각관내에서 상변화물질의 응고에 관한 실험적 연구 (An Experimental Study on Freezing of Phase Change Material in a Cooled Vertical Tube)

  • 이재목;이채문;임장순
    • 대한설비공학회지:설비저널
    • /
    • 제13권4호
    • /
    • pp.223-229
    • /
    • 1984
  • Experiments were performed for freezing of an initially superheated or nonsuperheated liquid phase in a cooled vertical tube. The liquid was placed in a copper tube whose surface maintained a uniform temperature during the data run and the freezing occurred in a copper tube. The phase change medium was n-odtadecane, a paraffin which freezes at about $61^{\circ}C$. Measurements were made which yielded information about the time dependence of the freezing front, of the amount of frozen mass, and of the various energy components extracted from the tube. The time-wise decay of the initial liquid superheat was also measured. Initial superheat of the liquid tends to moderately diminish the rozen mass and associated latent energy extraction at small times but has lit tie effect on these quantities at large tiems. Natural convection in the liquid Plays a modest role only at small times and disappears when the superheat decay to zero. Although the latent energy constitutes the largest contributor to the total extracted energy, the sensible energy components can make a significant contribution, especially at large tube wall subcoolings, large initial liquid superheating and short freezing time.

  • PDF

원자로 제어봉과 결합된 하이브리드 히트파이프의 CFD 해석 (CFD Analysis of a Concept of Nuclear Hybrid Heat Pipe with Control Rod)

  • 정영신;김경모;김인국;방인철
    • 한국유체기계학회 논문집
    • /
    • 제17권6호
    • /
    • pp.109-114
    • /
    • 2014
  • After the Fukushima accident in 2011, it was revealed that nuclear power plant has the vulnerability to SBO accident and its extension situation without sufficient cooling of reactor core resulting core meltdown and radioactive material release even after reactor shutdown. Many safety systems had been developed like PAFS, hybrid SIT, and relocation of RPV and IRWST as a part of steps for the Fukushima accident, however, their applications have limitation in the situation that supply of feedwater into reactor is impossible due to high pressure inside reactor pressure vessel. The concept of hybrid heat pipe with control rod is introduced for breaking through the limitation. Hybrid heat pipe with control rod is the passive decay heat removal system in core, which has the abilities of reactor shutdown as control rod as well as decay heat removal as heat pipe. For evaluating the cooling performance hybrid heat pipe, a commercial CFD code, ANSYS-CFX was used. First, for validating CFD results, numerical results and experimental results with same geometry and fluid conditions were compared to a tube type heat pipe resulting in a resonable agreement between them. After that, wall temperature and thermal resistances of 2 design concepts of hybrid heat pipe were analyzed about various heat inputs. For unit length, hybrid heat pipe with a tube type of $B_4C$ pellet has a decreasing tendency of thermal resistance, on the other hand, hybrid heat pipe with an annular type $B_4C$ pellet has an increasing tendency as heat input increases.

급배수시스템에서 잔류염소 농도 균등화를 위한 재염소 처리 (Rechlorination for residual chlorine concentration equalization in distribution system)

  • 김진근;한지안
    • 상하수도학회지
    • /
    • 제28권1호
    • /
    • pp.91-101
    • /
    • 2014
  • Three water treatment plants(WTPs) in Jeju island whose source water have different characteristics from those of the mainland of Korea were investigated. Coefficients of bulk water decay($k_b$) of free chlorine at $5^{\circ}C$ for ES, GJ, NW WTPs were $-0.003hr^{-1}$, $-0.002hr^{-1}$ and $-0.001hr^{-1}$ respectively based on bottle tests. To simulate the free chlorine variations in the distribution system using EPANET, ES WTP was chosen. Free chlorine concentrations of several sites were less than the drinking water quality standards(i.e., 0.1 mg/L); E5(0.03 mg/L), E6(0.02 mg/L), W21(0.02 mg/L) and W25(0.03 mg/L). To maintain more than 0.1 mg/L of free chlorine in the distribution system, at least 1.9 mg/L of chlorine was needed at the WTP, which suggested rechlorination was needed to supply palatable tap water to customers. Two sites, one that diverged into E5 and E6 in the east-line and another located before E21 in the west-line were selected for the appropriate rechlorination locations. The recommended rechlorination dosages were 0.42 mg/L for the east and 0.27 mg/L for the west. The simulated results indicated that the free chlorine could be reduced to 0.4 mg/L at the WTP with rechlorination, and taps with excessive free chlorine could be more stabilized(i.e., 0.1~0.4 mg/L).

배.급수관망의 잔류염소 확보를 위한 적정 재염소 주입량 산정 및 효과분석 (Computing the Dosage and Analysing the Effect of Optimal Rechlorination for Adequate Residual Chlorine in Water Distribution System)

  • 김도환;이두진;김경필;배철호;주혜은
    • 대한환경공학회지
    • /
    • 제32권10호
    • /
    • pp.916-927
    • /
    • 2010
  • 일반적으로 정수처리 공정에서 염소에 의한 소독공정은 수인성 질병을 억제하고 상수도관망에서 미생물의 재성장을 억제하는 목적으로 사용되고 있다. 그러나 염소소독은 수중의 유기물과 반응하여 소독부산물(Disinfection By-products; DBPs) 과 같은 발암성 물질을 생성함으로 적절한 염소 주입이 필요하고 최근에는 관말지역에서의 잔류염소 확보를 위해 상수관로 나 배수지 등에서 재염소를 실시하는 경향이 증가하고 있는 추세이다. 따라서 본 연구에서는 정수장에서 최적의 염소주입과 재염소 주입량을 산정하기 위하여 미국 EPA에서 개발한 EPANET 2.0을 사용하여 최적 염소 주입량을 산정하고 그 효과를 모의하였다. 대상지역 상수관로에 대한 수질을 모의하기 위하여 bottle test를 통해 수체감소계수($k_{bulk}$)를 도출하였으며, syster-matic analysis method를 이용하여 관벽감소계수($k_{wall}$)를 도출하였다. 배ㆍ급수계통에서의 수질을 정확히 예측하고자 유량과 체류시간 등을 고려한 수리해석 모델을 기초로 하여 상수도관망에서의 잔류염소 농도를 예측하고 염소주입 농도에 따른 소독부산물(DBPs)인 트리할로메탄(Trihalomethanes; THMs)의 생성변화를 실험을 통해 확인하였다. 수체감소계수($k_{bulk}$)를 도출한 결과 온도가 높을수록 초기에 빠른 감소를 보였으며, $25^{\circ}C$의 경우 25시간이 지난 이후에는 절반이상이 감소하였다. 대상지역에 재염소 주입시설을 도입할 경우 최적 재염소 주입량을 산정하였으며, 관망도상에서 경제적으로 유리한 지점을 선정할 수 있었다.

1/10 축소모형을 이용한 소공연장의 흡음재와 확산체의 적용위치에 따른 음향성능 비교 (Comparison of Acoustic Performance Depending on the Location of Sound Absorptive and Diffuser in Small Auditoriums Using 1/10 Scale Models)

  • 김태희;박찬재;박지훈;한찬훈
    • 한국음향학회지
    • /
    • 제34권2호
    • /
    • pp.146-156
    • /
    • 2015
  • 본 연구는 흡음재와 확산체의 적용위치가 소공연장의 음향성능에 미치는 영향에 대하여 알아보았다. 서울의 대학로의 2000년 이후 개관한 36곳의 공연장의 평균크기로 소공연장의 표준모델을 설정하여 연구를 진행하였다. 본 연구에서는 마감재 적용유효면적이 가장 작은 뒷벽을 기준으로 마감재의 적용면적을 산출하고, 마감재의 적용위치별 음향성능 변화를 분석하기 위하여 천장, 측벽의 적용위치를 전반부, 중반부, 후반부로 구분하여 총 8가지의 경우를 만들어, 1/10 축소모형실험을 진행하였다. 사용된 음향지표는 잔향시간(Reverberation Time, RT), 초기감쇠시간(Early Decay Time, EDT), 음악명료도(Clarity, C80), 음성명료도(Definition, D50), 음성전달지수(Speech Transmission Index, STI)를 이용하였다. 실험결과 마감재의 적용위치 변화는 소리의 울림에 양과 관련된 음향인자인 잔향시간, 초기감쇠시간 은 최소 변화 감지폭에 의한 (Just Noticeable Difference, JND) 평가시 변화가 뚜렷하게 나타났고, 소리의 명료도와 관련된 인자인 음악명료도, 음성명료도, 음성전달지수는 변화가 거의 없는 것으로 나타났다. 짧은 잔향시간을 얻고자 하는 경우 흡음재와 확산체 적용시 모두 측벽부분을 통한 잔향시간 조절이 가장 효과적이며, 측벽 전반부가 가장 짧은 잔향시간을 얻을 수 있는 위치인 것으로 나타났다.

성덕대왕신종(聖德大王神鍾) 당목(撞木)의 수종(樹種)과 열화(劣化) (Species Identification and Weathering of Wooden Striker on the Divine Bell of King Songdok)

  • 강애경
    • 박물관보존과학
    • /
    • 제4권
    • /
    • pp.71-78
    • /
    • 2003
  • 성덕대왕신종 당목의 수종과 오랜 세월동안 외부적인 요인(태양빛, 수분, 온도, 공기)에 의한 열화를 조사하였다. 당목의 수종은 느티나무(느릅나무과, Zelkova serrata)로 밝혀졌다. 열화로 인한 변화를 육안으로 관찰하였을 때 표면변색, 할렬, 목재면의 거칠어짐이 나타났다. 미세형태학적인 변화는 열화형태에 따라 세 부분(I, II, III-spot)으로 나누어 관찰하였다. I-spot에는 재색으로 변색됨과 동시에 조직의 관찰이 불가능할 정도로 먼지층이 완전히 조직을 뒤덮고 있었다. 그와 달리 변색이 되었지만 조직의 관찰이 가능한 II-spot는 무수한 균사와 세포내강에 유입된 먼지 등의 오염물이 관찰되었다. 세포벽은 열화로 인해 물리적인 강도를 소실하여 약화되어 있으며 그로 인해 세포벽의 미세한 할렬과 찢김 등을 관찰할 수 있었다. 균사가 세포를 뒤덮고 있지만 그로 인한 목재 부후는 관찰되지 않았다. 표면에서 불과 0.5 mm 아래의 III-spot는 목재의 고유한 적갈색을 유지하고 있으며 세포벽은 건전재와 유사하였다. 이상의 변화들은 목재부후와는 구별되었으며 표면에서 불과 0.5 mm 이하의 지극히 표면적인 현상이라고 할 수 있다.

자연순환 루프에서 이상유동 특성에 관한 예비실험 연구 (Preliminary Experimental Study on the Two-phase Flow Characteristics in a Natural Circulation Loop)

  • 김재철;하광순;박래준;홍성완;김상백
    • 한국전산유체공학회:학술대회논문집
    • /
    • 한국전산유체공학회 2008년도 춘계학술대회논문집
    • /
    • pp.308-311
    • /
    • 2008
  • As a severe accident mitigation strategy in a nuclear power plant, ERVC(External Reactor Vessel Cooling) has been proposed. Under ERVC conditions, where a molten corium is relocated in a reactor vessel lower head, a natural circulation two-phase flow is driven in the annular gap between the reactor vessel wall and its insulation. This flow should be sufficient to remove the decay heat of the molten corium and maintain the integrity of the reactor vessel. Preliminary experimental study was performed to estimate the natural circulation two-phase flow. The experimental facility which is one dimensional, the half height, and the 1/238 channel area of APR1400, was prepared and the experiments were carried out to estimate the natural circulation two-phase flow with varying the parameters of the coolant inlet area, the heat rate, and the coolant inlet subcooling. In results, the periodic circulation flow was observed and the characteristics were varied from the experimental parameters. The frequency of the natural circulation flow rate increased as the wall heat flux increased.

  • PDF