• 대한기계학회논문집B
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• 제28권11호
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• pp.1398-1406
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• 2004

The nonlinear signals from an impedance meter for the area average void fraction in two-phase flow have been analyzed to construct a phase space trajectory. The pseudo phase space was constructed with the time delay and proper dimensions. The time delay and the embedding dimension were chosen by the average mutual information and by the false nearest neighborhood, respectively. The attractor-density-map of projected states was used to produce the two dimensional probability distribution functions (2D-PDF). Since the developed 2D-PDF showed clear distinction of the flow patterns, the flow regime identification was made with three rules and with the 2D-PDF. Also, the transition criteria of Mishima-Ishii agree well with the present results.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2004년도 추계학술대회논문집
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• pp.879-882
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• 2004

Two-phase flow exists in many industrial components. Characteristics of two-phase flow have been studied by many researchers; however, a further study of the two-phase is required for flow-induced vibration. Characteristics of two-phase flow were measured by force sensor at the end of a vertical pipe. The predominant frequency of fluctuation was obtained for various speeds of flow pattern. A correlation to slug frequency for horizontal flow was obtained by Heywood & Richardson (1979), while Legius et al (1997) for vertical flow. A coefficient based on the correlation is estimated and then compared to the existing ones. The existing empirical formulations for average void fraction were proposed by Wallis (1969), Zuber et al (1967) and Ishii (1970). In the present result, flow parameters, such as flow quality and real velocity, are evaluated with void fraction.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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• pp.502-507
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• 1998

Two different types the CANDU fuel bundles hue been modeled for the ASSERT-IV code subchannel analysis. From calculated values of mixture enthalpy and void paction distributions in the fuel bundles, it is found that net buoyancy effect is pronounced in the central region of the DUPIC fuel bundle when compared with the standard CANDU fuel bundle. It is also found that the central region of the DUPIC fuel bundle can be cooled more efficiently than that of the standard fuel bundle. From calculated mixture enthalpy distribution at the exit of fuel channel, it is found that the mixture enthalpy and void fraction can be highest in the peripheral region of the DUPIC fuel bundle. On the other hand, the enthalpy and the void fraction were found to be highest in the central region of the standard CANDU fuel bundle at the exit of the fuel channel. This study shows that the subchannel analysis is very useful assessing thermal behavior of the fuel bundle that could be used in CANDU reactors.

• 한국추진공학회지
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• 제21권2호
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• pp.32-40
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• 2017

탄소섬유/에폭시 복합재의 기공함유율을 정량적으로 평가하기 위한 절차를 제시하였다. 고려한 복합재는 두 종류이며 오토클레이브 공법과 필라멘트와인딩 공법에 의해 제작하였다. 탄소섬유/에폭시 복합재의 기공함유율은 공기 중에서와 물 속에서의 무게에서 구한 복합재의 밀도와 구성재의 밀도, 그리고 산처리법과 고온연소법을 적용하여 구한 무게함유율과 부피함유율을 이용하여 평가하였다. 또한 FE-SEM을 통해 탄소섬유 표면을 관찰하여 복합재 내의 수지 제거 여부도 조사하였다. 연구결과에 따르면 복합재 내의 수지는 산처리법이나 고온연소법을 적용하면 충분히 제거할 수 있으며 구성재의 무게함유율과 부피함유율 그리고 복합재의 기공함유율은 본 연구에서 제시된 절차를 적용하면 정량적으로 평가할 수 있다.

• 대한기계학회논문집B
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• 제26권11호
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• pp.1559-1569
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• 2002

In order to investigate the characteristics of electromagnetic flowmeter in two -phase flow, an AC electromagnetic flowmeter was designed and manufactured. In various flow conditions, the signals and noises from the flowmeter were obtained and analyzed by comparison with the observed flow patterns with a high speed CCD camera. The experiment with the void simulators in which rod shaped non-conducting material was used was carried out to investigate the effect of the bubble position and the void fraction on the flowmeter. Based on the results from the void simulator, two -phase flow experiments encompassed from bubbly to slug flow regime were conducted. The simple relation $\Delta$ $U_{TP}$ = $\Delta$ $U_{SP}$ (l-$\alpha$) was verified with measurements of the potential difference and the void fraction. Due to the lack of homogeneity in a rent two -phase flow, the discrepancy between the relation and the present measurement was slightly increased with void fraction and also liquid volumetric flux jf. Whereas there is no difference in the shape of the raw signal between single-phase flow and bubbly flow, the signal amplitude for bubbly flow is higher than that for single -phase flow at the same water flow rate, since the passage area of the water flow is reduced. In the case of slug flow, the phase and the amplitude of the flowmeter output show dramatically the flow characteristics around each slug bubble and the position of a slug bubble itself. Therefore, the electromagnetic flowmeter shows a good possibility of being useful for identifying the flow regimes.ul for identifying the flow regimes.

• Nuclear Engineering and Technology
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• 제55권1호
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• pp.109-118
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• 2023

In this paper, the evaluation method of fluidelastic instability (FEI) of newly designed steam generator tubing in pressurized water reactor (PWR) nuclear power plants is discussed. To obtain the parameters for prediction of the critical velocity of FEI for steam generator tubes, experimental research is carried out, and the design parameters are determined. Using CFD numerical simulation, the tube array scale of the model experiment is determined, and the experimental device is designed. In this paper, 7 groups of experiments with void fractions of 0% (water), 10%, 20%, 50%, 75%, 85% and 95% were carried out. The critical damping ration, fundamental frequency and critical velocity of FEI of tubes in flowing water were measured. Through calculation, the total mass and instability constant of the immersed tube are obtained. The critical damping ration measured in the experiment mainly included two-phase damping and viscous damping, which changed with the change in void fraction from 1.56% to 4.34%. This value can be used in the steam generator design described in this paper and is conservative. By introducing the multiplier of frequency and square root of total mass per unit length, it is found that the difference between the experimental results and the calculated results is less than 1%, which proves the rationality and feasibility of the calculation method of frequency and total mass per unit length in engineering design. Through calculation, the instability constant is greater than 4 when the void fraction is less than 75%, less than 4 when the void fraction exceeds 75% and only 3.04 when the void fraction is 95%.

• 한국해안·해양공학회논문집
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• 제20권2호
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• pp.157-167
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• 2008

본 연구에서는 직립 구조물 전면에서 발생하는 권파에 의한 월파의 기포분율을 수리모형실험으로 검토하였다. 구조물 직립벽 전면에서 쇄파되는 내습파랑은 쇄파와 월파 과정동안 기포를 연행하거나 액적화되며 강한 난류세기를 갖는 다위상흐름이 된다. 본 연구에서는 광섬유반사율계와 기포를 이용한 영상유속계기법으로 월파의 기포분율, 유속, 그리고 층두께를 측정하였다. 반복된 실험으로 얻어진 기포분율과 유속은 조화평균과 시간평균을 적용하여 분석하였다. 평균된 기포분율의 분포로부터 높은 기포분율은 주로 월파수괴의 전면부에서 발생하는 것을 알 수 있었으며, 구조물 상단표면에 접한 영역과 월파수괴의 후면부 영역은 상대적으로 낮은 기포분율을 보여주었다. 측정된 월파의 기포분율, 유속, 그리고 층두께로부터 월파의 흐름율과 운동량을 산정하였고, 실험결과로부터 기포분율이 중요한 인자임을 알 수 있었다. 수심평균된 기포분율, 유속, 두께의 상사적 분포특성을 이용하여 경험식을 제시하였고, 1차원적 경험식을 이용하여 흐름율과 운동량을 검토하였다.

• 대한기계학회논문집
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• 제11권5호
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• pp.856-866
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• 1987

본 연구에서는 동심원관에서 기-수 이상류가 상향과 하향유동을 하는 경우에 대하여 시간평균 국부보이드율을 계측하여 확률밀도함수를 구하고, 이들로부터 통계량 인 분산도, 비대칭도계수, 첨도계수를 계산하여, 이들 값과 유동양식을 관련시켜 유동 양식의 판별기준을 정량적으로 제시하는데 목적이 있다. 또한 환상간제과 간제의 반 경방향 입치 및 유동양식에 따르는 시간평균국부보이드율의 변동을 구명하는데도 목적 을 두어 일차적으로 상향유동 경우에 대한 연구결과를 보고한다.

• Nuclear Engineering and Technology
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• 제51권5호
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• pp.1241-1250
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• 2019

This study mainly focused on the neutronics modeling of bubbles in bubbly flow in boiling water reactors. The bubble, ring and homogenous models were used for radial void fraction distribution. Effect of the bubble and ring models on the infinite multiplication factor and two-group flux distribution was investigated by comparing with the homogenous model. Square pitch unit cell geometry was used in the calculations. In the bubble model, spherical and non-spherical bubbles at random positions, sizes and shapes were produced by Monte Carlo method. The results show that there are significant differences among the proposed models from the viewpoint of physical interaction mechanism. For the fully-developed bubbly flow, $k_{inf}$ is overestimated in the ring model by about $720{\pm}6pcm$ with respect to homogeneous model whereas underestimated in the bubble model by about $-65{\pm}9pcm$ with a standard deviation of 15 pcm. In addition, the ring model shows that the coolant must be separated into regions to properly represent the radial void distribution. Deviations in flux distributions principally occur in certain regions, such as corners. As a result, the bubble model in modeling the void fraction can be used in nuclear engineering calculations.

• Nuclear Engineering and Technology
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• 제50권8호
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• pp.1266-1276
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• 2018

In this paper, three-dimensional neutronic calculations were performed in order to calculate the dependency of CRW on the temperature of fuel and moderator and the moderator void. Calculations were performed using the known MTR_PC computer codes in the core configuration 61 of TRR. The dependency of CRW on the fuel temperature in the range of $20-340^{\circ}C$ and the moderator temperature of each control rods were studied. Based on the positions of the control rods, the calculations were performed in three different cases, named case A, B and C. By the results, the worth of each control rods increases by increasing of the coolant temperature in all methods, however, the total CRW is somewhat independent of the fuel temperature. In addition, the results showed that the variation of CRW versus density depends on the positions of the control rods and the most change in CRW in the coolant temperature, $20-100^{\circ}C$ (279 pcm), belongs to SR4. Finally the effect of void on CRW was studied for different void fraction in coolant. The most worth change is about $2 for 40% void fraction related to SR1 and SR3 in case B. For 40% void fraction, the total CRW increases about $7.5, $6 and $7 in cases, A, B and C, respectively.