• 제목/요약/키워드: vertical annulus

검색결과 55건 처리시간 0.021초

Slim hole 환형관내 고-액 2상 유동에 관한 연구 (Solid-liquid two phase helica l flow in a Rotating Annulus)

  • 한상목;우남섭;황영규;김영주
    • 한국전산유체공학회:학술대회논문집
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    • 한국전산유체공학회 2008년도 춘계학술대회논문집
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    • pp.369-372
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    • 2008
  • An experimental study is carried out to study two-phase vertically upward hydraulic transport of solid particles by water in a vertical and inclined (0${\sim}$60 degree) concentric annulus with rotation of the inner cylinder. Rheology of particulate suspensions in shear-thinning fluids is of importance in many applications such as particle removal from surfaces, transport of proppants in fractured reservoir and cleaning of drilling holes, and so on. Annular fluid velocities varied from 0.2 m/s to 1.5 m/s for the actual drilling operational condition. Macroscopic behavior of solid particles, averaged flow rate, and particle rising velocity are observed. Main parameters considered in this study were radius ratio, inner-pipe rotary speed, fluid flow regime, and particle injection rate. For both water and CMC solutions, the higher the concentration of the solid particles is, the larger the pressure gradients become

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Critical Heat Flux in Uniformly Heated Vertical Annulus Under a Wide Range of Pressures 0.57 to 15.0 MPa

  • Chun, Se-Young;Chung, Heung-June;Hong, Sung-Deok;Yang, Sun-Kyu;Chung, Moon-Ki
    • Nuclear Engineering and Technology
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    • 제32권2호
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    • pp.128-141
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    • 2000
  • The critical heat flux (CHF)experiments have been carried out in a wide range of pressures for an internally heated vertical annulus. The experimental conditions covered ranges of pressures from 0.57 to 15.01 MPa, mass fluxes of 0 kg/$m^2$s and from 200 to 650 kg/$m^2$s, and inlet subcoolings from 85 to 413 kJ/kg. The characteristics of the present data and the effect of pressure on CHF are discussed. Most of the CHFs were identified to dryout of the liquid film in the annular or annular-mist flow. For the mass flux of 200 kg/$m^2$s, there were the indications that the CHF occurred at the transition from annular to annular-mist How in the pressure range of 3~10 MPa. For the mass fluxes of 550 and 650 kg/$m^2$s, the CHFs had a maximum value at a pressure of 2~3 MPa, and the pressure at the maximum CHF values had a trend moving toward the pressure at the peak value of pool boiling CHF as the mass flux decreased. The CHF data under a zero mass flux condition indicate that both the effects of pressure and inlet subcooling on the CHF were smaller, compared with those on the CHF with net water upward flow.

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방향성 소구경 굴착의 입자 이송특성에 관한 연구 (An Experimental Study of Cuttings Transport in Directional Slim Hole Drilling)

  • 한상목;김정환;황영규;우남섭;김영주
    • 한국해양공학회지
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    • 제26권2호
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    • pp.20-25
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    • 2012
  • During drilling, the precipitation velocity of cuttings within an annulus depends on the density and configuration of the cuttings, and on the density, viscosity, and rheological characteristics of the drilling fluid. In directional drilling in particular, it is difficult to adjust and control the cuttings. In contrast to vertical drilling, it is very important to evaluate the flow characteristics of a drilling flow field. However, research on the transfer features of cuttings is inadequate. In this study, in order to identify transfer features of cuttings, an experiment was performed under wide-ranging conditions by constructing a slim hole annulus ($44mm{\times}30mm$) device. In this experiment, the particle volume fraction were influenced by particle size, particle concentration within the flow, pipe rotation, flow volume, and inclination of the annulus. In addition, a mathematical formula for volumetric concentration was deduced and compared to the test results and behavior of cuttings under the other drilling condition was made to be predicted. Therefore, this study can provide meaningful data for vertical and horizontal drilling, and for directional drilling.

Critical Heat Flux for Low Flow in Vertical Annulus under Various Pressure Conditions

  • Chun, Se-Young;Jun, Hyung-Gil;Chung, Heung-June;Moon, Sang-Ki;Chung, Moon-Ki
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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    • pp.386-391
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    • 1997
  • It is important to understand correctly a CHF under low flow condition for the purpose of enhancing the reactor safety and performance in the LWRs. The CHF experiments have been carried out for an internally heated vertical annulus in RCS loop facility. The experimental conditions cover ranges of pressure from 1.82 to 12.08 MPa, mass flux from 300 to 550kg/$m^2$. s and inlet subcooling of 210kJ/kg. The CHF data decrease with increasing pressure at high value of mass flux. For mass flux of about 300kg/$m^2$. s, the CHF rue little influenced by pressure. The CHF data are correlated well by using the dimensionless heat flux and dimensionless mass flux for a fixed inlet subcooling except the data group of 12.08 MPa. It seems that the Doerffer correlation and Katto correlation overestimate the CHF for low pressure and lower value of mass flux within this experimental ranges. The Bowling correlation gives a better prediction than the other two correlations.

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Assessment of CHF Correlations for Internally Heated Concentric Annulus Channels

  • Park, Jae-Wook;Baek, Won-Pil;Chang, Soon-Heung
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1996년도 춘계학술발표회논문집(2)
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    • pp.325-330
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    • 1996
  • The existing CHF correlations for internally heated concentric annulus channels are assessed using KAIST CHF database for uniformly heated vertical annuli. Six annulus correlations (Jannsen-Kervinen. Barnett, Levitan-Lantsman, Kumamaru et al., Doerffer et al., and Bobkov et at.) are chosen for assessment based on literature survey and Groeneveld et al.'s CHF table for round tube is also assessed for comparison. Among the above correlations, two are inlet-condition type and others local conditions type. To make the comparison meaningful, the local-condition-type correlations are assessed in two ways: direct substitution method (DSM) and heat balance condition method (HBM). Totally 1174 data are classified into 10 groups based on pressure and mass flux conditions and correlations are assessed to each group separately. Prediction capability of each correlation depends on the data group and none shows the best prediction over the entire group. In overall, the correlations by Doerffer et al. and Jannsen et al. appear to be the best, but Barnett or Levitan-Lantsman correlations also show reasonable prediction for most groups. However, the low-pressure, ]ow flow CHFs are not well predicted by any correlations. The CHF table for round tubes overpredicts the CHF in annuli at fixed local conditions.

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An Experimental Study on Heat Transfer Characteristics Just Before Critical Heat Flux in Uniformly Heated Vertical Annulus Under a Wide Range of Pressures

  • Chun, Se-Young;Moon, Sang-Ki;Chung, Heung-June;Chung, Moon-Ki
    • Nuclear Engineering and Technology
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    • 제34권4호
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    • pp.269-285
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    • 2002
  • Water heat transfer experiments were carried out in a uniformly heated annulus with a wide range of pressure conditions. The local heat transfer coefficients for saturated water (low boiling have been measured just before the occurrence of the critical heat flux (CHF) along the length of the heated section. The trends of the measured heat transfer coefficients were quite different from the conventional understanding for the heat transfer of saturated flow boiling. This discrepancy was explained from the nucleate boiling in the liquid film of annular flow under high heat flux conditions. The well-known correlations were compared with the measured heat transfer coefficients. The Shah and Kandlikar correlations gave better prediction than the Chen correlation. However, the modified Chen correlation proposed in the present work showed the best agreement with the present data among correlations examined .

EFFECTS OF GEOMETRIC PARAMETERS ON NUCLEATE POOL BOILING OF SATURATED WATER IN VERTICAL ANNULI

  • Kang, Myeong-Gie
    • Nuclear Engineering and Technology
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    • 제41권3호
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    • pp.271-278
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    • 2009
  • Nucleate pool boiling of water in vertical annuli at atmospheric pressure has been studied experimentally and two empirical correlations have been suggested to obtain effects of geometric parameters on heat transfer. Data of the present and the previous tests range over a tube length of 0.50-0.57 m, a diameter of 16.5-34.0 mm, and an annular gap size of 3.7-44.3 mm. Through the analysis, tube bottom confinement (open or closed) has been investigated, as well. The developed correlations predict experimental data within a ${\pm}25%$ error bound. It has been identified that effects of the diameter and the length of heated tubes as well as the annular gap size should be counted into the analyses to estimate heat transfer coefficients accurately.

기계판막을 판륜상연에 위치시킨 대동맥판 치환술 (Alternative Technique of Aortic Valve Replacement -Implantation of Mechanical Aortic Valve at a Supra-Annular Level-)

  • 최종범;이삼윤
    • Journal of Chest Surgery
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    • 제29권5호
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    • pp.504-509
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    • 1996
  • 대동맥 판 치환술시 봉합법으로써 단순봉합(simple interrupted suture), 8자형 봉합(figure of eight su- ture), 수평 석상봉합법 (horizontal mattress suture method) 등이 이용되고 있다. 그러나 심내막염에 의 해 판륜이 손상되거나 퇴행성 변성으로 판륜이 약화된 환자들에서는 본봉합법으로대동맥판 치환이 어려 울 수 있고,치환후 판막주위 누출등의 합병증이 발생할수 있다. 저자들은 1993년 6월부터 1995년 6월 까지 심내막염에 의한 대동맥판 환자 4례,퇴행성 판막환자 3례,류마티스성 판막병변 환자 1례에서 수직 석상봉합법 (vertical mattress suture method)으로 기계판막(mechanical valve)을 판륜 상연에 위치시 키는 술식을 시행하였다. . 2례에서 농양으로 판륜이 결손되어 자가심막편을 이용하여 결손부위를 봉합하였다. 판막 치환을 위 해 2-0 polyester 봉합사를 이용했고, 봉합사를 지지하는 테프론 조각을 심실쪽에 위치시키고 침사가 심 실쪽에서 발살바동쪽으로 통과하도록 하는 수직 석상봉합법을 이용하였다. 본 수술방법으로 최소한 19mm기계판막의 사용은 완전히 배제할 수 있었다. 술후 평균 13.3개월에 심에코 검사로 추적 관찰한 \ulcorner과, 판막운동의 이상은 발생하지 않았으며, 판막자체에서 발생하는 압력 경사는 3례에서 6mmHg이 하였고 5례에서 20내지 40mmHg였다 이와같은 결과에서 판륜이 손상되거나 약화된 대동맥판 환자에 서 판막치환술시 수직 석상 봉합법을 이용하여 기계판막을 판륜상연에 위치시키므로써 수술이 용이하 고 술후 합병증을 감소시킬 수 있을 것으로 사료된다.

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