Benchmarking of the CUPID code to the ASSERT code in a CANDU channel
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The CUPID code was developed and is continuously updated in KAERI. Verification and validation (V&V) is mainly done for light water reactors (LWRs). This paper describes a benchmarking of the detailed mesh level compared with sub-channel level for application to pressurized heavy water reactors (PHWRs), even though component scale comparison for the PHWR moderator system was done once before. We completed a sub-channel level comparison between the CUPID code and the ASSERT code and a CUPID code analysis. Because the ASSERT code has already been validated with numerous experiments, benchmarking with the ASSERT code will offer us more trust on the CUPID code. The target channel has high power and thus high pressure deformation. The high power channel tends to have a high possibility of critical heat flux (CHF), because a high void fraction and quality in channel exit region appear. In this research, after determining the reference grid and T/H model, we compared the sub-channel level results of the CUPID code with those of the ASSERT code
Abstract
The CUPID code was developed and is continuously updated in KAERI. Verification and validation (V&V) is mainly done for light water reactors (LWRs). This paper describes a benchmarking of the detailed mesh level compared with sub-channel level for application to pressurized heavy water reactors (PHWRs), even though component scale comparison for the PHWR moderator system was done once before. We completed a sub-channel level comparison between the CUPID code and the ASSERT code and a CUPID code analysis. Because the ASSERT code has already been validated with numerous experiments, benchmarking with the ASSERT code will offer us more trust on the CUPID code. The target channel has high power and thus high pressure deformation. The high power channel tends to have a high possibility of critical heat flux (CHF), because a high void fraction and quality in channel exit region appear. In this research, after determining the reference grid and T/H model, we compared the sub-channel level results of the CUPID code with those of the ASSERT code
참고문헌 (14)
- Y. F. Rao, "ASSERT-PV 3.2:advanced subchannel thermal hydraulics code for CANDU fuel bundles", Nucl. Eng. Des, 275, pp.69~79 (2014)
- A. Nava-Dominguez, "Assessment of subchannel code ASSERT-PV for flow-distribution predictions", Nucl. Eng. Des, 275, pp.122~132 (2014)
- J.J. JEONG, "THE CUPID CODE DEVELOPMENT AND ASSESSMENT STRATEGY", Nuclear Engineering and Technology, 42(6), pp.636~655 (2010), 한국원자력학회
- H. Y. Yoon, "Recent improvements in the CUPID code for a multi-dimensional two-phase flow analysis of nuclear reactor components", NET, 42(6), pp.635~655 (2010)
- J. R. Lee, "Numerical study for CANDU moderator temperature prediction by using the two-phase flow analysis code, CUPID", Ann. Nucl. Energy, 59, pp.139~148 (2013)
- S. R. Choi, "Numerical investigation of the CANDU moderator thermal-hydraulics using the CUPID code", Prog. Nucl. Energy, 85, pp.541~547 (2015)
- 이승준, "CUPID코드의 유체 물성치 변화를 고려한 자연대류 해석", 한국전산유체공학회지, 20(4), pp.14~20 (2015), 한국전산유체공학회[DOI]
- CUPID Code Manuals, "J. R. Lee", KAERI, ~, pp.KAERI (2016), TR-6528
- M. H. A. Piro, "Fluid flow investigations within a 37CANDU fuel bundle supported by magnetic resonance velocimetry and computational fluid dynamics", Int. J. Heat Fluid Flow, 66, pp.27~42 (2017)
- Zheng Lu, "Computational fluid dynamics investigations of flow through an aged CANDU pressure tube", Appl. Sci. Nucl. Eng (2021), University of Ontario Institute of Technology
- 이경근, "Multilevel modeling of diametral creep in pressure tubes of Korean CANDU units", Nuclear Engineering and Technology, 53(12), pp.4042~4051 (2021), 한국원자력학회[DOI]
- S. J. Lee, "Improvement of the two-fluid momentum equation using a modified Reynolds stress model for horizontal turbulent bubbly flows", Chem. Eng. Sci, 173, pp.208~217 (2017)
- Avramova Maria, "DEVELOPMENT OF AN INNOVATIVE SPACER GRID MODEL UTILIZING COMPUTATIONAL FLUID DYNAMICS WITHIN A SUBCHANNEL ANALYSIS TOOL", Doctor, pp.2007
- M. H. A. Piro, "Progress in on-going experimental and computational fluid dynamics investigations within a CANDU fuel channel", Nucl. Eng. Des, 299, pp.184~200 (2015)