http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
전규동,임재혁,심재우 한국공업화학회 1998 응용화학 Vol.2 No.1
There were many studies on critical heat flux(CHF) during last several decades, In recent years CHF correlations have been supported by local and non-local hypothesis. In this study we have found that CHF can be predicted by local variables only; namely, CHF is independent of heated length.
웨스팅하우스형 원자력발전소 가압기 방출 탱크의 실시간 시뮬레이션을 위한 전문모델 개발
서재승,전규동 한국시뮬레이션학회 2004 한국시뮬레이션학회 논문지 Vol.13 No.2
The thermal-hydraulic model ARTS which was based on the RETRAN-3D code adopted in the domestic full-scope power plant simulator which was provided in 1998 by KEPRI. Since ARTS is a generalized code to model the components with control volumes, the smaller time-step size should be used even if converged solution could not get in a single volume. Therefore, dedicated models which do not force to reduce the time-step size are sometimes more suitable in terms of a real-time calculation and robustness. In the case of PRT(Pressurizer Relief Tank) model, it is consist of subcooled water in bottom and non-condensable gas in top. The sparger merged under subcooled water enhances condensation. The complicated thermal-hydraulic phenomena such as condensation, phase separation with existence of non-condensable gas makes difficult to simulate. Therefore, the PRT volume can limit the time-step size if we model it with a general control volume. To prevent the time-step size reduction due to convergence failure for simulating this component, we developed a dedicated model for PRT. The dedicated model was expected to provide substantially more accurate predictions in the analysis of the system transients. The results were resonable in terms of accuracy, real-time simulation, robustness and education of operators, complying with the ANSI/ANS-3.5-1998 simulator software performance criteria and RETRAN-3D results.
W/H형 원전 시뮬레이터용 핵 증기공급 계통 열수력모델 ARTS(Advanced Real-time Thermal Hydraulic Simulation)의 보조계산체계 개발
서재승,전규동 한국에너지학회 2004 에너지공학 Vol.13 No.1
국내에 설치 운영중인 원전 훈련용 시뮬레이터의 핵 증기공급 계통 열수력 프로그램은 1980년 전후에 외국 벤더들이 개발하여 공급한 것으로 이들 열수력 프로그램은 핵 증기공급 계통 열수력 현상을 실시간으로 모의하기 위해 과도하게 단순화된 모델을 채택하고 있다. 그결과 원자로 냉각계통에 복잡한 이상유동이 발생하는 사고를 모의하는 경우 정확도가 떨어질 수 있어 부정적인 훈련(Negative training)을 초래할 가능성이 있다. 이와같은 문제를 해결하기 위해 전력연구원에서는 RETRAN-3D 코드를 기본으로 시뮬레이터용 핵 증기공급 계통 열수력 프로그램 ARTS 코드를 개발하였다. RETRAN-3D 코드를 기본으로 하는 ARTS 코드는 거의 대부분의 사고를 실시간으로 모의할 수 있으며 계산의 건전성도 보장된다. 그러나, 대형냉각재 상실사고나 저압 저유속 상태의 장기 과도현상 등을 모의하는 경우에 발생하는 계산실패나 실시간 계산 지체등의 가능성이 있다. 이 경우 이를 자동으로 대체 보완할 수 있는 보조계산체계를 개발했다. 특히, ARTS 코드의 실시간 계산 및 건전성 문제가 예상되는 대형냉각재 상실사고를 주 모의 대상으로 간주했다. 계산 결과는 코드의 정확도, 실시간 계산능력, 건전성 및 운전원 교육등에서 최종안정성평가보고서 및 ANSI/ANS-3.5-1998[1] 시뮬레이터 소프트웨어 기준을 만족하는 것으로 평가되었다.
Shane Park,전규동 대한기계학회 2011 JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY Vol.25 No.11
When a liquid droplet impacts on a solid surface, it recoils to the center of that surface after reaching its maximum spreading diameter. The mechanism of droplet recoiling is not fully understood. To simulate this recoiling of a droplet, a particle method is a good choice because it does not require grids for simulating fluid motions, and can easily handle a large deformation of fluid. In this study, the coupled method of rigid body dynamics and the moving particle semi-implicit (MPS) method (Park and Jeun, 2011) was used to calculate three-dimensional droplet impingement. Also, the previous surface tension model for MPS (Nomura et al., 2001) was revised to get a more realistic surface tension force. A two-step calculation was performed. In the first step, a MPS calculation was performed with particles that were considered to have no mass or volume. In the second step, rigid body dynamics came into the calculation and considered the diameters of particles being slightly lesser than the initial distance between particles. In this study, the calculated results were compared with the measured data (Kim and Chun, 2000) and the recoiling lengths of droplets for the various initial impingement speeds were estimated.
신도영,정의주,전규동,김성중 한국유체기계학회 2016 한국유체기계학회 논문집 Vol.19 No.4
Objective of this study is to compare the inherent characteristics of natural convection flow inside the canister of spent fuel dry storage system with different backfill gases by utilizing computational fluid dynamics (CFD) code. Four working fluids were selected for comparison study. Helium currently used backfill gas for canister, air, nitrogen, and argon are frequently used as coolant in many heat transfer applications. The results indicate that helium has very distinct conductive behavior and show very weak natural convective flow compared to the others. Argon showed the strongest natural convective flow but also the worst coolability. Air and nitrogen showed similar characteristics to each other. However, due to difference in Prandtl number, nitrogen showed more effective natural convective flow. These results suggest that experimental validation for the nitrogen is needed to investigate the potential coolability other than currently commercially used helium.