2방정식 난류모델을 이용한 축소 APR+ 내부 유동분포 수치해석

다국어 초록 (Multilingual Abstract)

Complex thermal hydraulic characteristics exist inside the reactor because the reactor internals consist of fuel assembly, internal structures and so on. In this study, to examine the effect of Reynolds-Averaged Navier-Stokes (RANS)-based two-equation turbulence models in the analysis of flow distribution inside a 1/5 scaled-down APR+, simulation was performed using the commercial computational fluid dynamics software, ANSYS CFX R.13 and the predicted results were compared with the measured data. It was concluded that reactor internal flow pattern was locally different depending on the turbulence models. In addition, the prediction accuracy of k-ε model was superior to that of other two-equation turbulence models and this model predicted the relatively uniform distribution of core inlet flow rate.

목차 (Table of Contents)

• Abstract
• 1. 서론
• 2. 해석모델
• 3. 수치모델링
• 4. 결과
• 5. 결론
• References

참고문헌 (Reference)

1 이공희, "칼란드리아 내부의 감속재 열유동 해석을 위한 난류모델 성능 평가" 대한기계학회 36 (36): 363-369, 2012

2 이공희, "축소 APR+ 원자로 모형에서의 내부유동분포 수치해석" 대한기계학회 37 (37): 855-862, 2013

3 Rohde, U., "Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor-validation of CFD codes" 237 : 1639-1655, 2007

4 Kim, K. H., "Experimental study of the APR+ reactor core flow and pressure distributions under 4-pump running conditions" 256 : 957-966, 2013

5 이공희, "CFD 우수사례 지침을 적용한 관 다발 주위의 난류유동 수치해석" 대한기계학회 37 (37): 961-969, 2013

6 Menter, F., "CFD best practice guidelines for CFD code validation for reactor safety applications" ECORA CONTRACT 2001

7 "ANSYS CFX-Solver Modeling Guide"

8 "ANSYS CFX, Version 13.0"

9 Lee, B. J., "A review on the regionalization methodology for core inlet flow distribution map" 33 : 441-456, 2001

10 Lee, G. H., "A numerical study for the effect of flow skirt geometry on reactor internal flow" 62 : 452-462, 2013

11 어동진, "A FLOW AND PRESSURE DISTRIBUTION OF APR+ REACTOR UNDER THE 4-PUMP RUNNING CONDITIONS WITH A BALANCED FLOW RATE" 한국원자력학회 44 (44): 735-744, 2012