• Journal of the Korean Society of Propulsion Engineers
• /
• v.5 no.3
• /
• pp.33-40
• /
• 2001

In order to investigate the operating characteristics of a supersonic steam ejector, the axisymmetric, compressible, Reynolds-averaged, Wavier-Stokes computations are performed using a finite volume method. The secondary and back pressures of the ejector system with a second throat are changed to investigate their effects on the suction mass flow. Three operation modes of the steam ejector system, the critical mode, subcritical mode and back flow mode, are discussed to predict the critical suction mass flow. The present computations are validated with some experimental results. The secondary and back pressures of the supersonic steam ejector significantly affect the critical suction mass flow. The present computations predict the experimented critical mass flow with fairly good accuracy A good correlation is obtained for the critical suction mass flow. The present results show that provided the primary nozzle configuration and secondary pressure are blown, we can predict the critical mass flow with good accuracy.

• Journal of computational fluids engineering
• /
• v.7 no.2
• /
• pp.43-52
• /
• 2002

This paper presents the numerical methodology of ATHOS3 code for thermal hydraulic analysis of steam generators in nuclear power plant. Topics include porous media approach, governing equations, physical models and correlations for solid-to-fluid interaction and heat transfer, and numerical solution scheme. The ATHOS3 code is applied to the thermal hydraulic analysis of steam generator in the Korea Kori Unit-1 nuclear power plant and the computed results are presented

• Proceedings of the KSME Conference
• /
• 2001.06d
• /
• pp.828-833
• /
• 2001

In this study, an analysis tool to assess the susceptibility of steam generator tubes due to the flow-induced vibration was developed. The fluid-elastic instability analysis of the U-tube bundle for CE-type steam generator was accomplished. The effective mass distribution along the U-tube was obtained to calculate the natural frequency and dynamic mode shape. Finally, stability ratios for selected tubes are obtained.

• Proceedings of the KSME Conference
• /
• 2001.06e
• /
• pp.463-468
• /
• 2001

This paper presents the methodology for thermal hydraulic analysis of Pressurized Water Reactor (PWR) steam generators. Topics include porous media approach, governing equations, physical models and correlations for solid-to-fluid interaction and heat transfer and numerical solution scheme. Some details about the ATHOS3 code currently used widely for thermal hydraulic analysis of PWR steam generators in the industry are presented. The ATHOS3 code is applied to the thermal hydraulic analysis of steam generator in the Korea YGN 3&4 nuclear power plant and the computed results are presented.

• Transactions of the Korean Society of Mechanical Engineers
• /
• v.18 no.8
• /
• pp.2177-2183
• /
• 1994

The rapid expansion or condensible gas such as moist air of steam gives rise to nonequilibrium condensation. As a result of irreversibility of condensation process in the supersonic cascade flow of low pressure steam turbine, the entropy of the flow is increased, and the efficiency of the turbine is decreased. In the present study, to investigate the flow of moist air in 2-dimensional cascade made as the configuration of the tip section of the last actual steam turbine moving blade, the static pressure at both sides of pressure and suction of blade are measured by static pressure taps and the distribution of Mach number on both surfaces of the blade are obtained by using the measured static pressure. Also, the flow field is visualized by a schlieren system. From the experimental results, the effects of the stagnation temperature and specific humidity on the flow properties in a 2-dimensional stationary cascade of a practical steam turbine blade are clearly identified.

• Journal of Energy Engineering
• /
• v.9 no.4
• /
• pp.358-365
• /
• 2000

본 연구에서는 수직 단일관에서의 재관수(reflux) 응축 현상에서 증기유량이 역류제한치보다 큰 경우에 발생하는 다양한 유동 패턴을 예측하고, 그 동적 특성을 해석하기 위한 모델을 개발하였다. 특히 L/D가 큰 재관수 응축기에서 발생하는 충전 방출 모드에서의 동적 특성을 예측하는 것이 목표이다. 응축기의 내부를 액체와 증기의 두 영역으로 나누어 질량, 에너지, 운동량 보존에 입각한 본 모델은, 형성된 물기둥의 진동시 갈래질 경계(bifurcation boundary)와 진동주기를 예측할 수 있다. 이 모델은 McMaster 대학에서 수행한 실험결과와 비교한 결과 양호한 예측을 했고, 튜브 직경변화 효과를 잘 묘사하였다. 이러한 단순 모델은 재관수 응축기의 설계시에 설계변수를 도출하는데 사용될 수 있고, 인위적으로 부여한 압력펄스를 이용하여 재관수 응축기의 운전영역을 개선하는데 기초로 활용될 수 있다.

• 한국전산유체공학회:학술대회논문집
• /
• 2004.10a
• /
• pp.127-130
• /
• 2004

In this study, three-dimensional numerical calculations are peformed to simulate the flow and heat transfer in helically coiled tube steam generator employing a commercial CFD (Computational Fluid Dynamics) code. The problem considered herein includes the boiling phase change flow of tube side fluid and the single-phase counter-current flow of shell side hot fluid transferring heat to the tube side flow thru the tube wall. Detailed investigations are performed for both shell-side and tube-side flow fields in terms of density and volume fractions of each phase of fluids as well as for the tube wall heat transfer field in terms of heat transfer coefficients.

• 한국신재생에너지학회:학술대회논문집
• /
• 2007.11a
• /
• pp.613-616
• /
• 2007

A pilot scale circulating fluidized bed for refuse derived fuel is developed and constructed in order to demonstrate efficient and safe utilization of waste fuel. The capacity of the facility is 8 steam tons per hour with the steam quality of $450^{\circ}C$ and 38atm. The quantity and the quality of the produced steam is sufficient to produce 1MWe power capacity. The test operation proved the high combustion efficiency of 99% and up. The emissions of NOx, SOx in flue gas are below 100, 60ppm respectively with out any emission control. HCl emissions were above 400ppm at the combustor exit but reduced below 10ppm after scrubber.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1997.10a
• /
• pp.573-578
• /
• 1997

기존 냉각수 주입 계통의 안전성 및 신뢰도를 높이려는 노력에서 미국, 일본, 이태리 등 여러 나라에서는 증기 주입기에 대한 분석 기법 개발과 실험을 통한 연구가 활발하게 진행되고 있다. 이들이 이상 유동 현상이 일어나는 혼합 노즐을 해석하기 위해 사용한 방법은 제어체적 분석기법으로, 이 분석 방법에서는 응축 메커니즘을 고려할 수 없다. 본 연구에서는 이러한 사항을 개선하기 위해 혼합 노즐 해석시 one dimensional two fluid model을 적용하여 상간의 운동량 및 에너지 전달을 고려함으로써 비교적 정확하게 해석 모델 및 코드를 개발하였고, 출력 변수인 방출 압력과 방출 온도를 계산하였으며, 개발한 해석 코드를 검증 및 분석을 하기 위해 ANL 실험자료를 근거로 하였다. 개발한 코드에 의해 계산된 방출 압력은 ALN 실험치에 비해 높은 경향을 보여 주었지만 ANL에서 제어 체적 분석 기법을 적용하여 이론식으로 계산한 값보다는 비교적 정확한 경향을 보여 주었다.

• Proceedings of the Korean Nuclear Society Conference
• /
• 2001.10a
• /
• pp.175.2-175
• /
• 2001