• 항공우주시스템공학회지
• /
• 제12권2호
• /
• pp.15-22
• /
• 2018

7개의 방정식으로 구성된 DIM을 사용하여 압축성 다상 유동에 대해 연구하였다. 액체와 기체의 상세한 경계면 유동 구조를 얻기 위해 5 차의 MLP와 변형된 HLLC 근사 리만 해법을 포함하는 고차 수치기법이 구현되었다. 수치 방법의 유효성 검증을 위해 물과 공기로 구성된 다양한 1차원 충격관 문제를 해석하였고, 불연속면에 대해 뛰어난 해상도를 얻을 수 있었다. 마하수 1.22의 충격파 조건에서의 2차원 공기-헬륨 기포에 대한 충격파 상호 작용을 수치 해석하였고, 충격파 현상들을 잘 모사하였으며 실험결과와 비교 검증하였다.

• Journal of Power Electronics
• /
• 제19권4호
• /
• pp.968-979
• /
• 2019

Recently, there has been increased interest in the study of multiphase machines due to their higher fault-tolerant capability when compared to their conventional three-phase counterparts. For six-phase machines, stator windings configured with a single isolated neutral (1N) provide significantly more post-fault torque/power than two isolated neutrals (2N). Hence, this configuration is preferred in applications where post-fault performance is critical. It is well known that min-max injection has been commonly used for three-phase and multiphase machines in healthy condition to maximize the modulation limit. However, there is a lack of discussion on min-max injection for post-fault condition. Furthermore, the effects in terms of the common-mode voltage (CMV) in modulating signals has not been discussed. This paper investigates the effect of min-max injection in post fault-tolerant control on the voltage and speed limit of a symmetrical six-phase induction machine with single isolated neutral. It is shown that the min-max injection can minimize the amplitude of reference voltage, which maximizes the modulation index and post-fault speed of the machine. This in turn results in a higher post-fault power.

• Nuclear Engineering and Technology
• /
• 제53권6호
• /
• pp.1810-1820
• /
• 2021

Study of single bubble behavior under rolling motions can prove useful for fundamental understanding of flow field inside the modern small modular nuclear reactors. The objective of the present study is to simulate the influence of rolling conditions on single rising bubble in a liquid using multiphase Moving Particle Semi-implicit (MPS) method. Rolling force term was added to 2D Navier-Stokes equations and a computer program was written using C language employing OpenACC to port the code to GPU. Computational results obtained were found to be in good agreement with the results available in literature. The impact of rolling parameters on trajectory and velocity of the rising bubble has been studied. It has been found that bubble rise velocity increases with rolling amplitude due to modification of flow field around the bubble. It has also been concluded that the oscillations of free surface, caused by rolling, influence the bubble trajectory. Furthermore, it has been discovered that smaller vessel width reduces the impact of rolling motions on the rising bubble. The effect of liquid viscosity on bubble rising under rolling was also investigated and it was found that effects of rolling became more pronounced with the increase of liquid viscosity.

• Nuclear Engineering and Technology
• /
• 제52권12호
• /
• pp.2821-2835
• /
• 2020

The phenomenon identification and ranking table (PIRT) is an important basis in the nuclear power plant (NPP) thermal-hydraulic analysis. This study focuses on the importance ranking of the input parameters when lacking the PIRT, and the target scenario is the small break loss of coolant accident (SBLOCA) in a pressurized water reactor (PWR) CPR1000. A total of 54 input parameters which might have influence on the figure of merit (FOM) were identified, and the sensitivity measure of each input on the FOM was calculated through an optimized moment-independent global sensitivity analysis method. The importance ranking orders of the parameters were transformed into the Savage scores, and the parameters were categorized based on the Savage scores. A parameter importance ranking table for the SBLOCA scenario of the CPR1000 reactor was obtained, and the influences of some important parameters at different break sizes and different accident stages were analyzed.

• Nuclear Engineering and Technology
• /
• 제55권10호
• /
• pp.3754-3767
• /
• 2023

Turbulent jet discharges in subcooled water pools are essential for safety systems in nuclear power plants, specifically in the pressure suppression pool of boiling water reactors and In-containment Refueling Water Storage Tank of advanced pressurized water reactors. The gas and liquid flow in these systems is investigated using multiphase flow analysis. This field has been extensively examined using a combination of experiments, theoretical models, and Computational Fluid Dynamics (CFD) simulations. ANSYS CFX offers two approaches to model multiphase flow behavior. The non-homogeneous Eulerian-Eulerian Model has been used in this work; it computes global information and is more convenient to study interpenetrated fluids. This study utilized the Large Eddy Simulation Model as the turbulence model, as it is better suited for non-stationary and buoyant flows. The CFD results of this study were validated with experimental data and theoretical results previously obtained. The figures of merit dimensionless penetration length and the dimensionless buoyancy length show good agreement with the experimental measurements. Correlations for these variables were obtained as a function of dimensionless numbers to give generality using only initial boundary conditions. CFD numerical model developed in this research has the capability to simulate the behavior of non-condensable gases discharged in water.

• Nuclear Engineering and Technology
• /
• 제52권4호
• /
• pp.721-733
• /
• 2020

In nuclear engineering, the occurrence of critical heat flux (CHF) is complicated for rod bundle, and it is much more difficult to predict the CHF when it is in natural circulation under motion condition. In this paper, the dryout-type CHF is investigated for the rod bundle in a natural circulation loop under rolling motion condition based on the coupled analysis of subchannel method, a one-dimensional system analysis method and a CHF mechanism model, namely the three-fluid model for annular flow. In order to consider the rolling effect of the natural circulation loop, the subchannel model is connected to the one-dimensional system code at the inlet and outlet of the rod bundle. The subchannel analysis provides the local thermal hydraulic parameters as input for the CHF mechanism model to calculate the occurrence of CHF. The rolling motion is modeled by additional motion forces in the momentum equation. First, the calculation methods of the natural circulation and CHF are validated by a published natural circulation experiment data and a CHF empirical correlation, respectively. Then, the CHF of the rod bundle in a natural circulation loop under both the stationary and rolling motion condition is predicted and analyzed. According to the calculation results, CHF under stationary condition is smaller than that under rolling motion condition. Besides, the CHF decreases with the increase of the rolling period and angular acceleration amplitude within the range of inlet subcooling and mass flux adopted in the current research. This paper can provide useful information for the prediction of CHF in natural circulation under motion condition, which is important for the nuclear reactor design improvement and safety analysis.

• 한국수자원학회논문집
• /
• 제52권10호
• /
• pp.697-706
• /
• 2019

다상흐름 모델링 기법과 하이브리드 난류 모델링 기법을 결합한 수치모형을 이용하여 사각형 수로에서의 중력류를 수치모의 하였다. 이 연구에서 적용한 다상흐름 해석기법은 밀도가 큰 중력류 유체, 상대적으로 밀도가 작은 주변류 유체 그리고 자유수면 위에서 흐르는 공기를 3개의 상으로 처리하며, 각 상에 대해서 분리된 흐름 지배방정식을 적용한다. 난류흐름은 벽경계 근처에서는 RANS 모드로 모의하고 벽에서 떨어진 영역에서는 LES 모드로 해석하는 하이브리드 RANS/LES 방법의 일종인 IDDES 기법을 이용하여 해석한다. 이 연구에서 적용한 모델링 기법은 중력류의 머리의 전파속도를 실험값과 일치하게 잘 예측하는 것으로 나타났다. 수치해석 결과는 아울러 낮은 레이놀즈수 난류모형을 이용한 RANS 수치모의에서 이용되는 정도의 격자해상도에서도 큰 규모의 Kelvin-Helmholtz 형식의 경계면 와의 발달과 이들 와가 지속적으로 3차원 형식의 붕괴를 거쳐 작은 난류구조로 분해되면서 난류에너지가 소산되는 현상을 성공적으로 예측함을 보여준다. 적용한 수치모의 기법은 공학적으로 접근 가능한 격자해상도에서 돌출-쪼개짐 흐름 불안정을 동반한 중력류 머리부분의 3차원 거동 특성을 잘 재현하며, 이 결과는 보다 높은 격자해상도에서 구해진 LES 결과에 상응하는 것으로 나타났다. 이 연구결과는 하이브리드 난류모델링 기법과 다상흐름 해석기법을 병합한 수치모형이 자연상태에서 복잡한 중력류의 물리적 거동을 예측하는데 공학적으로 유망한 방법임을 보여준다.

• 한국가시화정보학회지
• /
• 제14권1호
• /
• pp.9-14
• /
• 2016

• 천문학회보
• /
• 제17권
• /
• pp.9.1-9.1
• /
• 1992

• 한국수자원학회:학술대회논문집
• /
• 한국수자원학회 1995년도 학술발표회 논문집
• /
• pp.219-227
• /
• 1995