Assessment of MARS-KS prediction capability for natural circulation flow in passive heat removal system
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Considering that system analysis codes are used for the evaluation of the performance of Passive Safety Systems (PSSs), it is important to investigate the capability of the system analysis code to reliably predict the heat transfer and natural circulation flow, which are the main phenomena governing the performance of a PSS. Since MARSKS has been widely validated for heat transfer models, this study focuses on evaluating its capability to predict the single and two-phase pressure drops and natural circulation flow. The straight pipe simulation results indicate that the pressure drop predictions are reliable within ±5 % error margin for the single-phase flow and the errors of pressure drop up to 30 % for the two-phase flow. Through single-phase natural circulation flow analysis, it is concluded that the use of the appropriate K-factor modeling based on the flow regimes is important since the natural circulation flow rate in MARS-KS is mainly affected by the form loss factor modeling. With twophase natural circulation flow analysis, this study emphasizes the behavior of the system could change significantly depending on the two-phase wall friction and pressure loss modeling. With the analysis results, modeling considerations for the PSS performance evaluation with the system analysis codes are proposed.
Abstract
Considering that system analysis codes are used for the evaluation of the performance of Passive Safety Systems (PSSs), it is important to investigate the capability of the system analysis code to reliably predict the heat transfer and natural circulation flow, which are the main phenomena governing the performance of a PSS. Since MARSKS has been widely validated for heat transfer models, this study focuses on evaluating its capability to predict the single and two-phase pressure drops and natural circulation flow. The straight pipe simulation results indicate that the pressure drop predictions are reliable within ±5 % error margin for the single-phase flow and the errors of pressure drop up to 30 % for the two-phase flow. Through single-phase natural circulation flow analysis, it is concluded that the use of the appropriate K-factor modeling based on the flow regimes is important since the natural circulation flow rate in MARS-KS is mainly affected by the form loss factor modeling. With twophase natural circulation flow analysis, this study emphasizes the behavior of the system could change significantly depending on the two-phase wall friction and pressure loss modeling. With the analysis results, modeling considerations for the PSS performance evaluation with the system analysis codes are proposed.
참고문헌 (36)
- T. L. Schulz, "Westinghouse AP1000 advanced passive plant", Nucl. Eng. Des, 236, pp.1547~1557 (2006)
- B. Bae, "Design of condensation heat exchanger for the PAFS(passive Auxiliary Feedwater system)of APR+(advanced power reactor Plus)", Ann. Nucl. Energy, 46, pp.134~143 (2012)
- H. Ha, "Optimal design of passive containment cooling system for innovative PWER", Nucl. Eng. Technol, 49(5), pp.941~952 (2017)
- ESBWR Design Control Document Tier, vol. 2, "GE Hitachi Nuclear Energy", ~, pp.26A6642AD Rev. 09 (2010)
- K. H. Bae, "Enhanced safety characteristics of SMART100 adopting passive safety systems", Nucl. Eng. Des, 379, pp.111247~
- Galassi, Methodology for the evaluation of the reliability of passive system, "F. D’Auria", university of pisa, 1~34, pp.DIMNP NT 420 (00) (2000)
- M. Marqu`es, "Methodology for the reliability evaluation of a passive system and its integration into a probabilistic safety assessment", Nucl. Eng. Des, 235, pp.2612~2631 (2005)
- A. K. Nayak, "Passive System reliability analysis using APSRA methodology", Nuclear, Eng. Des, 238, pp.1430~1440 (2008)
- A. K. Nayak, "A review: passive system reliability analysis -accomplishments and unresolved issues", Front. Energy Res, 2 (2014)[DOI]
- J. Lee, "Effect evaluation on performance issues of passive safety system – Part I. Passive heat removal system", Nucl. Eng. Des, 403, pp.112160~ (2023)
- J. Lee, "Effect evaluation on performance issues of passive safety system – Part II. Passive emergency core cooling system", Nucl. Eng. Des, 411, pp.112446~ (2023)
- RELAP5, "MOD3. 3 code manual Volume IV:models and correlations", V. H. Ransom, 2001
- MARS-KS Code Manual, "Korea Institute of Nuclear Safety", ~, pp.KINS (2022), RR-1822
- Y. S. Bang, "Improvements of condensation heat transfer models in MARS code for laminar flow in presence of non-condensable gas", Nucl. Eng. Technol, 41, pp.1015~1024 (2009)
- Assessment of the Wall Film Condensation Model with Non-condensable Gas in RELAP5, "MOD3 and TRACE for Vertical Tube and Plate Geometries", J. Lee, 2019, NUREG[DOI]
- S. S. Jeon, "Assessment of horizontal intube condensation models using MARS code. Part I : stratified flow condensation", Nucl. Eng. Des, 254, pp.254~265 (2013)
- S. S. Jeon, "Assessment of horizontal intube condensation models using MARS code. Part II : annular flow condensation", Nucl. Eng. Des, 262, pp.510~524 (2013)
- S. S. Jeon, "Prediction of nucleate boiling heat transfer on horizontal U-shaped heat exchanger submerged in a pool of water using MARS code", Nucl. Eng. Des, 295, pp.317~337 (2015)
- S. S. Jeon, "Development of heat transfer model package for horizontal U-shaped heat exchanger submerged in pool of passive safety system", Nucl. Technol, 196, pp.303~318 (2016)
- Two phase pressure drop in straight pipes and channels:water steam mixtures at 600 to 1400 psia, "E. Janssen", General Electric Co. Atomic Power Equipment Dept, ~, pp.GEAP-4616 (1964)
- Developing two phase flow in tubes and annuli, "E. Janssen", general electric Co, ~, pp.GEAP-10341 (1971)
- S. M. Seyyedi, "Numerical and experimental analysis of a rectangular single phase natural circulation loop with asymmetric heater position", Int. J. Heat Mass Tran, 130, pp.1343~1357 (2019)
- A Generalized Correlation for the Steady State Flow in Single Phase Natural Circulation Loops, "P. K. Vijayan", Bhabha AtomicC Research Centre, ~, pp.BARC (2000), 2000[DOI]
- O. J. Mendler, "Natural circulation tests with water at 800 to 2000 psia under non boiling, local boiling, and bulk boiling conditions", J. Heat Tran, 83(3), pp.261~273 (1961)
- K. H. Kang, "Separate and integral effect tests for validation of cooling and operational performance of the APR+passive auxiliary feedwater system", Nucl. Eng. Technol, 44(6), pp.597~610 (2012)
- D. J. Zigrang, "A review of explicit friction factor equations, Transactions of ASME", Journal of Energy Resource Technology, 107, pp.280~283 (1985)
- C. F. Colebrook, "Turbulent flow in pipes with particular reference to the transition region between smooth and rough pipe laws", Journal of Institute of Civil Engineers, 11, pp.133~156 (1939)
- Flow of Fluids through Valves, Fittings and Pipes. Metric Edition-SI Units, "CoNY. Crane", Crane Co, ~, pp.Technical Paper No. 410M (1982)
- B. T. Swapnalee, "A generalized flow equation for single phase natural circulation loops obeying multiple friction laws", Int. J. Heat Mass Tran, 54, pp.2618~2629 (2011)
- One-Dimensional Drift-Flux Model and Constitue Equations for Relative Motion between Phases in Various Two-phase Flow Regimes, "M. Ishii", Argonne National Laboratory Argonne, ~, pp.ANL-77-47 (1977)
- R. Lockhart, "Proposed correlation of data for isothermal two-phase, two-component flow in pipes", Chem. Eng. Prog, 45(1), pp.39~48 (1949)
- K. T. Claxton, "HTFS correlations for two-phase pressure drop and void fraction in tubes" (1972), Heat Transfer and Fluid Flow Service
- G. F. Yao, "Wall friction in annular-dispersed two-phase flow", Nucl. Eng. Des, 163, pp.149~161 (1996)
- J. H. Yang, "Assessment of wall friction model in multi-dimensional component of MARS with air-water cross flow experiment", Nucl. Eng. Des, 312, pp.106~120 (2017)
- C. J. Choi, "Effect of wall friction model on predicting emergency core coolant behavior in upper downcomer with direct vessel safety injection using MARS-KS", Ann. Nucl. Energy, 116, pp.395~406 (2018)
- S. G. Shin, "Comparative study of constitutive relations implemented in RELAP5 and TRACE – Part I : methodology & wall friction", Nucl. Eng. Technol, 54(9), pp.3526~3539 (2022)