Comparative study of CFD and 3D thermal-hydraulic system codes in predicting natural convection and thermal stratification phenomena in an experimental facility
2
조회
0
다운로드
1
인용
0
참고문헌
키워드
초록
Natural circulation phenomena have been nowadays largely revisited aiming to investigate the performances of passive safety systems in carrying-out heat removal under accidental conditions. For this purpose, assessment studies using CFD (Computational Fluid Dynamics) and also 3D thermal-hydraulic system codes are considered at different levels of the design and safety demonstration issues. However, these tools have not being extensively validated for specific natural circulation flow regimes involving flow mixing, temperature stratification, flow recirculation and instabilities. In the present study, an experimental test case based on a small-scale pool test rig experiment performed by Korea Atomic Energy Research Institute, is considered for code-to-code and code-toexperimental data comparison. The test simulation is carried out using the FLUENT and the 3D thermal-hydraulic system CATHARE-2 codes. The objective is to evaluate and compare their prediction capabilities with respect to the test conditions of the experiment. It was observed that, notwithstanding their numerical and modelling differences, similar agreement results are obtained. Nevertheless, additional investigations efforts are still needed for a better representation of the considered phenomena.
Abstract
Natural circulation phenomena have been nowadays largely revisited aiming to investigate the performances of passive safety systems in carrying-out heat removal under accidental conditions. For this purpose, assessment studies using CFD (Computational Fluid Dynamics) and also 3D thermal-hydraulic system codes are considered at different levels of the design and safety demonstration issues. However, these tools have not being extensively validated for specific natural circulation flow regimes involving flow mixing, temperature stratification, flow recirculation and instabilities. In the present study, an experimental test case based on a small-scale pool test rig experiment performed by Korea Atomic Energy Research Institute, is considered for code-to-code and code-toexperimental data comparison. The test simulation is carried out using the FLUENT and the 3D thermal-hydraulic system CATHARE-2 codes. The objective is to evaluate and compare their prediction capabilities with respect to the test conditions of the experiment. It was observed that, notwithstanding their numerical and modelling differences, similar agreement results are obtained. Nevertheless, additional investigations efforts are still needed for a better representation of the considered phenomena.
참고문헌 (20)
- Audrius Grazevicius, "Numerical investigation of two-phase natural convection and temperature stratifi cation phenomena in a rectangular enclosure with conjugate heat transfer", Nuclear Engineering and Technology, 52(1), pp.27~36 (2020), 한국원자력학회
- Piotr Mazgaj, "Comparison of CATHARE-2results with the exper-imental results of cold leg intermediate break LOCA obtained during ROSA-2", LSTF test 7, 2016, pp.2, 1~[DOI]
- Modelling of ROCOM Mixing Test 2.2 with TRACE v5.0 Patch 3, "J. Kurki", ~, pp.NUREG (2015), IA-0454
- A. Bousbia Salah, "Assessment of the CATHARE-2 3D capabilities in predicting the temperature mixing under asymmetric buoyant driven flow conditions", Nucl. Eng. Des, 265, pp.469~483 (2013)
- A. Bousbia Salah, "Unsteady single-phase natural-circulation flow mixing prediction using 3-D thermal-hydraulic system and CFD codes", Nucl. Tech, 203, pp.293~314 (2018)
- S. Kim, "Experimental study on the thermal stratification in a pool boiling with a horizontal heat source", Ann. Nucl. Energy, 106, pp.235~246 (2017)
- August ANSYS, "ANSYS FLUENT User's Guide, 17.2, Release", ~ (2016)
- CATHARE-2 v25_3mod8.1 Code: General Description, "J. Darona", ~, pp.DEN, DANS[DOI]
- Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications, "J. Mahaffy", 5~, pp.NEA (2007), CSNI[DOI]
- Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications e Revision, "J. Mahaffy", 11~, pp.NEA (2014), CSNI[DOI]
- CFD Best Practice Guidelines for CFD Code Validation for Reactor - Safety Applications, "F. Menter", ~, pp.EU Project Evaluation of Computational Fluid Dynamic Methods for Reactor Safety Analysis (ECORA) under Contract No:FIKS-CT-2001-00154
- ERCOFTAC special interest group on quality and trust in industrial CFD, "M. Casey", Sulzer Innotec, Fluid Dynamics Laboratory, ~ (2000)
- ANSYS, "Module 09: Best Practice Guidelines. Introduction to ANSYS Fluent, vol. 17, 0 Release", ~ (2016)
- August ANSYS, "ANSYS Fluent Theory Guide, 17.2, Release", ~ (2016)
- G. Maranzana, "Experimental estimation of the transient free convection heat transfer coefficient on a vertical flat plate in air", Int. J. Heat Mass Tran, 45, pp.3413~3427 (2002)
- J.H. Keenan, "Steam Tables: Thermodynamic Properties of Water, Including Vapor, Liquid, and Solid Phases" (1969), Wiley
- James, Margolis, "Engineering Plastics Handbook" (2006), McGraw-Hill Education
- Y. K. Godovsky, "Thermophysical Properties of Polymers" (1992), Springer Berlin
- N. P. Bansal, "Handbook of Glass Properties" (1986), Academic Press, Inc.
- C. S. Kim, "Thermophysical Properties of Stainless Steels", ANL, 75-55 (1976)