• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 1998년도 추계학술발표회요약집
• /
• pp.135-135
• /
• 1998

• 대한기계학회논문집
• /
• 제19권11호
• /
• pp.3022-3030
• /
• 1995

The irreversibility of condensation process in the supersonic flow of steam turbine cascade causes the entropy to increase and the total pressure loss to be generated. In the present study, in order to investigate the moist air flow in two dimensional steam turbine cascade made as the configuration of the last stage tip section of the actual steam turbine moving blade, the static and total pressures along suction side of the blade are measured by pressure taps and Pitot tube. The flow field is visualized by a Schlieren system. The effects of stagnation temperature and the degree of supersaturation on energy loss and entropy change in the flow are clearly identified.

• 대한기계학회논문집
• /
• 제14권5호
• /
• pp.1311-1319
• /
• 1990

본 연구에서는 작동유체로서 습증기와 거동이 유사한 습증기를 대기흡입식 간 헐 초음속 풍동을 이용하여, 팽창율이 일정한 노즐을 통하여 팽창시키는 경우에 대하 여 비평형 응축영역내 입치하는 경우에 대하여, 정체점 상태량의 변화에 기인되는 응 축 및 응축형격파가 경사형격파의 형상과 변화에 미치는 영향을 다음의 관점으로부터 연구하였다.

• Nuclear Engineering and Technology
• /
• 제17권1호
• /
• pp.45-52
• /
• 1985

가압 경수로의 소형 냉각재 사고시 증기 발생기 U-자관 내에서의 억류 응축 현상(reflux condensation phenomena)은 주요한 열제거 수단이 된다. 열제거 Mechanism이 순수히 역류 응축 현상에 의 할 때, 증기 발생기의 열제거 능력을 평가하기 위하여 원자로 증기 발생기의 U-자관을 모사하는 두개의 U-자 관을 가진 증기응축 장치를 제작하여 다음 두 가지의 실험을 수행하였다. 첫째로, U-자관속에서 역류 응축 현상이 일어날 때 증기의 유입량을 증가시켜 가면서 역류 응축이 일어나는 액체 막 길이 (filmwise reflux condensation length)를 측정하였다. 둘째로는 길이가 다른 두 개의 U-자관에 증기만을 유입시킬 때와 증기와 공기를 동시에 유입시킬 때에 대한 Flooding Point를 측정하여 U-자관의 길이와 비응축성 가스가 Flooding Point에 미치는 영향을 조사하였다. 그리고 수학적 모델을 이용한 이론적 측정값과 실험 Data를 비교하였다.

• 에너지공학
• /
• 제24권1호
• /
• pp.42-50
• /
• 2015

신형 원전의 피동격납건물냉각계통(PCCS: Passive Containment Cooling System)을 구성하는 단일 전열관의 열제거 성능을 평가하기 위해, 비응축성 기체 존재 시 수직 튜브 외벽에서 발생하는 증기의 응축 열전달에 대한 실험을 수행하였다. 외경 40 mm, 길이 1.0 m의 전열관 외벽에서 증기-공기 혼합물의 평균 열전달계수를 측정하였으며, 압력 2-4 bar, 공기의 질량분율 0.1-0.7의 범위에서 실험데이터를 수집하였다. 이를 통해 압력과 비응축성기체의 농도가 응축 열전달계수에 미치는 영향을 평가하였다. 실험결과를 기존의 열전달모델인 Uchida와 Dehbi의 상관식과 비교하였으며, 이들 상관식은 실험결과에 비해 상대적으로 열전달계수를 낮게 예측함을 확인하였다.

• Nuclear Engineering and Technology
• /
• 제31권5호
• /
• pp.486-497
• /
• 1999

The local heat transfer coefficient is experimentally investigated for the reflux condensation in a countercurrent flow between the steam-air mixture and the condensate, A single vertical tube has a geometry which is a length of 2.4m, inner diameter of 16.56mm and outer diameter of 19.05mm and is made of stainless steel. Air is used as a noncondensible gas. The secondary side has a shape of annulus around vertical tube and the lost heat by primary condensation is transferred to the coolant water. The local temperatures are measured at 11 locations in the vertical direction and each location has 3 measurement points in the radial direction, which are installed at the tube center, at the outer wall and at the coolant side. In three different pressures, the 27 sets of data are obtained in the range of inlet steam flow rate 1.348∼3.282kg/hr, of inlet air mass fraction 11.8∼55.0%. The investigation of the flooding is preceded to find the upper limit of the reflux condensation. Onset of flooding is lower than that of Wallis' correlation. The local heat transfer coefficient increases as the increase of inlet steam flow rate and decreases as the increase of inlet air mass fraction. As an increase of the system pressure, the active condensing region is contracted and the heat transfer capability in this region is magnified. The empirical correlation is developed by 165 data of the local heat transfer. As a result, the Jacob number and film Reynolds number are dominant parameters to govern the local heat transfer coefficient. The rms error is 17.7% between the results by the experiment and by the correlation.

• Nuclear Engineering and Technology
• /
• 제50권5호
• /
• pp.654-664
• /
• 2018

Self-pressurization analysis of the natural circulation integral nuclear reactor through a new dynamic model is studied. Unlike conventional pressurized water reactors, this reactor type controls the system pressure using saturated coolant water in the steam dome at the top of the pressure vessel. Self-pressurization model is developed based on conservation of mass, volume, and energy by predicting the condensation that occurs in the steam dome and the flashing inside the chimney using the partial differential equation. A simple but functional model is adopted for the steam generator. The obtained results indicate that the variable measurement is consistent with design data and that this new model is able to predict the dynamics of the reactor in different situations. It is revealed that flashing and condensation power are in direct relation with the stability of the system pressure, without which pressure convergence cannot be established.

• Nuclear Engineering and Technology
• /
• 제24권2호
• /
• pp.130-140
• /
• 1992

동방향 성층이상유동에서의 직접적촉 응축현상을 일차원 모델인 RELAP5/MOD2와 /MOD3를 이용하여 해석하였으며, 해석결과를 Northwestern의 실험결과와 비교·검토하였다. 해석결과 RELAP5의 공유열전달 모델은 동방향 성층이상유동에서 응축율을 비교적 잘 예측하고 있다. 그러나 공유접촉면에 파형이 생기는 경우는 물경계두께 및 국부 열전달계수는 유사한 범위로 일치할분 현상을 예측하는데 상당한 차이가 있다.

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 1999년도 춘계학술발표회요약집
• /
• pp.107-107
• /
• 1999

Direct-contact condensation experiments of atmospheric steam and steam/air mixture on subcooled water flowing co-currently in a rectangular channel are carried out uszng an infrared thermal camera system to develop a temperature measurement method. The inframetrics Model 760 Infrared Thermal Imaging Radiometer is used for the measurement of the temperature field of the water film for various flow conditions. The local heat transfer coefficient is calculated using the bulk temperature gradient along the (low direction. It is also found that the temperature profiles can be used to understand the interfacial condensation heat transfer characteristics according to the flow conditions such as noncondensable gas effects, inclination effect, and flow rates.

• Nuclear Engineering and Technology
• /
• 제56권3호
• /
• pp.1052-1065
• /
• 2024

Advanced Pressurized Water Reactors (APWRs) and Boiling Water Reactors (BWRs) employ a suppression pool as a heat sink to prevent containment overpressure. Steam can be discharged into the pool through multi-hole spargers or blowdown pipes in both normal and accident conditions. Direct Contact Condensation (DCC) creates sources of momentum and heat. The competition between these two sources determines the development of thermal stratification or mixing of the pool. Thermal stratification is of safety concern as it reduces the cooling capability compared to a completely mixed pool condition. In this work we develop a scaling approach to prediction of the thermal stratification in a water pool induced by steam injection through spargers. Experimental data obtained from large-scale pool tests conducted in the PPOOLEX and PANDA facilities, as well as simulation results obtained using validated codes are used to develop the scaling. Two injection orientations, namely radial injection through multi-hole Sparger Head (SH) and vertical injection through Load Reduction Ring (LRR), are considered. We show that the erosion rate of the cold layer can be estimated using the Richardson number. In this work, scaling laws are proposed to estimate both the (i) transient erosion velocity and (ii) the stable position of the thermocline. These scaling laws are then implemented into a 1D model to simulate the thermal behavior of the pool during steam injection through the sparger.