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Comparisons of performance and operation characteristics for closed- and open-loop passive containment cooling system design

  • Bang, Jungjin (School of Energy Systems Engineering, Chung-Ang University) ;
  • Jerng, Dong-Wook (School of Energy Systems Engineering, Chung-Ang University) ;
  • Kim, Hangon (Central Research Institute, Korea Hydro and Nuclear Power, Ltd.)
  • Received : 2020.07.30
  • Accepted : 2021.01.31
  • Published : 2021.08.25

Abstract

Passive containment cooling systems (PCCSs) have been actively studied to improve the inherent safety of nuclear power plants. Hered, we present two concepts, open-loop PCCS (OL-PCCS) and closed-loop PCCS (CL-PCCS), applicable to the PWR with a concrete-type containment. We analyzed the heat-removal performance and flow instability of these PCCS concepts using the GOTHIC code. In both cases, PCCS performance improved when a passive containment cooling heat exchanger (PCCX) was installed in the lower part of the containment building. The OL-PCCS was found to be superior in terms of heat-removal performance. However, in terms of flow instability, the OL-PCCS was more vulnerable than the CL-PCCS. In particular, the possibility of flow instability was higher when the PCCX was installed in the upper part of the containment. Therefore, the installation location of the OL-PCCS should be restricted to minimize flow instability. Conversely, a CL-PCCS can be installed without any positional restriction by adjusting the initial system pressure within the loop, which eliminates flow instability. These results could be used as base data for the thermo-hydraulic evaluation of PCCS in PWR with a large dry concrete-type containment.

Keywords

Acknowledgement

This research was partly supported by the Chung-Ang University research grant in 2019 and by a National Research Foundation of Korea (NRF) grant funded by the Korean government (MSIP: Ministry of Science, ICT and Future Planning) (No. NRF-2017M2B2B1072552).

References

  1. N. Aksan, H. Choi, J. Chung, J. Cleveland, F.S. D'Auria, N. Fil, O. Gimenez, M. Ishii, H. Khartabil, K. Korotaev, Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants, vol. 1624, IAEA-TECDOC, 2009.
  2. W. Zhou, B. Wolf, S. Revankar, Assessment of RELAP5/MOD3.3 condensation models for the tube bundle condensation in the PCCS of ESBWR, Nucl. Eng. Des. 264 (2013) 111-118. https://doi.org/10.1016/j.nucengdes.2012.08.041
  3. T.L. Schulz, Westinghouse AP1000 advanced passive plant, Nucl. Eng. Des. 236 (14-16) (2006) 1547-1557. https://doi.org/10.1016/j.nucengdes.2006.03.049
  4. C. Zhao, J. Chen, Dynamic characteristics of AP1000 shield building for various water levels and air intakes considering fluid-structure interaction, Prog. Nucl. Energy 70 (2014) 176-187. https://doi.org/10.1016/j.pnucene.2013.08.002
  5. A. Bakhmet'Ev, M. Bol'Shukhin, V. Vakhrushev, A. Khizbullin, O. Makarov, V. Bezlepkin, S. Semashko, I. Ivkov, Experimental validation of the cooling loop for a passive system for removing heat from the AES-2006 protective envelope design for the Leningradskaya nuclear power plant site, Atom. Energy 106 (3) (2009) 185-190. https://doi.org/10.1007/s10512-009-9150-1
  6. J. Xing, D. Song, Y. Wu, HPR1000: advanced pressurized water reactor with active and passive safety, Engineering 2 (1) (2016) 79-87. https://doi.org/10.1016/j.eng.2016.01.017
  7. B.G. Jeon, H.C. No, Thermal-hydraulic evaluation of passive containment cooling system of improved APR+ during LOCAs, Nucl. Eng. Des. 278 (2014) 190-198. https://doi.org/10.1016/j.nucengdes.2014.07.038
  8. S.G. Lim, D.H. Kim, J.M. Lee, S.W. Lee, H.G. Kim, H.C. No, Prediction of heat removal performance for passive containment cooling system using MARS-KS code version 1.14. Korea Nuclear Society Spring Meeting, Jeju, Republic of Korea, May 18-19, 2017, pp. 18-19.
  9. Z. Huang, W. Ma, Performance evaluation of passive containment cooling system of an advanced PWR using coupled RELAP5/Gothic simulation, Nucl. Eng. Des. 310 (2016) 83-92. https://doi.org/10.1016/j.nucengdes.2016.10.004
  10. S.W. Lee, S. Heo, H.U. Ha, H.G. Kim, The concept of the innovative power reactor, Nuclear Engineering and Technology 49 (7) (2017) 1431-1441. https://doi.org/10.1016/j.net.2017.06.015
  11. H. Ha, S. Lee, H. Kim, Optimal design of passive containment cooling system for innovative PWR, Nuclear Engineering and Technology 49 (5) (2017) 941-952. https://doi.org/10.1016/j.net.2017.03.005
  12. L. Changdong, J. Wenying, Y. Jiang, C. Wei, W. Ting, C. Cheng, X. Hong, Experimental and computational analysis of a passive containment cooling system with closed-loop heat pipe technology, Prog. Nucl. Energy 113 (2019) 206-214. https://doi.org/10.1016/j.pnucene.2019.01.004
  13. KHNP, Hanuel 3,4 Final Safety Analysis Report, 1998.
  14. E.P.M.F. Rahnm, Gothic Thermal Hydraulics Analysis Package User Manual Version 8.0 (QA), vol. 12, Numerical Applications Inc., 2012. NAI 8907-8909, Rev.
  15. M. Gavrilas, P. Hejzlar, N.E. Todreas, M.J. Driscoll, Gothic code evaluation of alternative passive containment cooling features, Nucl. Eng. Des. 166 (3) (1996) 427-442. https://doi.org/10.1016/S0029-5493(96)01259-9
  16. Z.Y. Hung, Y.M. Ferng, W.S. Hsu, B.S. Pei, Y.S. Chen, Analysis of AP1000 containment passive cooling system during a loss-of-coolant accident, Ann. Nucl. Energy 85 (2015) 717-724. https://doi.org/10.1016/j.anucene.2015.06.027
  17. G. Jimenez, M.K. Fernandez-Cosials, R. Bocanegra, C. Queral, Analysis of the equipment and instrumentation qualification criteria using 3D containment models, Nucl. Eng. Des. 323 (2017) 28-38. https://doi.org/10.1016/j.nucengdes.2017.07.038
  18. B.U. Bae, B.J. Yun, S. Kim, K.H. Kang, Design of condensation heat exchanger for the PAFS (passive auxiliary feedwater system) of APR+ (advanced power reactor plus), Ann. Nucl. Energy 46 (2012) 134-143. https://doi.org/10.1016/j.anucene.2012.03.029
  19. J. Bang, J.-H. Hwang, H.G. Kim, D.-W. Jerng, Parametric Analyses for the Design of a Closed-Loop Passive Containment Cooling System, Nuclear Engineering and Technology, 2020.
  20. C. Byun, D. Jerng, N. Todreas, M. Driscoll, Conceptual design and analysis of a semi-passive containment cooling system for a large concrete containment, Nucl. Eng. Des. 199 (3) (2000) 227-242. https://doi.org/10.1016/S0029-5493(00)00228-4
  21. E.P.M.F. Rahnm, Gothic Thermal Hydraulic Analysis Package Technical Manual Version 8.0(QA), vol. 19, Numerical Applications Inc., 2012. NAI 8907e06, Rev.
  22. M. Furuya, F. Inada, T. Van der Hagen, Flashing-induced density wave oscillations in a natural circulation BWR-mechanism of instability and stability map, Nucl. Eng. Des. 235 (15) (2005) 1557-1569. https://doi.org/10.1016/j.nucengdes.2005.01.006
  23. Y. Kozmenkov, U. Rohde, A. Manera, Validation of the RELAP5 code for the modeling of flashing-induced instabilities under natural-circulation conditions using experimental data from the CIRCUS test facility, Nucl. Eng. Des. 243 (2012) 168-175. https://doi.org/10.1016/j.nucengdes.2011.10.053
  24. S. Jiang, M. Yao, J. Bo, S. Wu, Experimental simulation study on start-up of the 5 MW nuclear heating reactor, Nucl. Eng. Des. 158 (1) (1995) 111-123. https://doi.org/10.1016/0029-5493(95)01020-I
  25. A. Manera, T.H. van der Hagen, Stability of natural-circulation-cooled boiling water reactors during startup: experimental results, Nucl. Technol. 143 (1) (2003) 77-88. https://doi.org/10.13182/NT03-A3399
  26. M. Ishii, Thermally Induced Flow Instabilities in Two-phase Mixtures in Thermal Equilibrium, Georgia Institute of Technology, 1971.
  27. Y. Zhang, G. Su, X. Yang, S. Qiu, Theoretical research on two-phase flow instability in parallel channels, Nucl. Eng. Des. 239 (7) (2009) 1294-1303. https://doi.org/10.1016/j.nucengdes.2009.02.018
  28. K. Fukuda, T. Kobori, Classification of two-phase flow instability by density wave oscillation model, J. Nucl. Sci. Technol. 16 (2) (1979) 95-108. https://doi.org/10.1080/18811248.1979.9730878
  29. N. Zuber, Flow excursions and oscillations in boiling, two-phase flow systems with heat addition. Symposium on Two-phase Flow Dynamics, Eindhoven EUR4288e, 1967, p. 1071.
  30. H. Liu, S. Kakac, F. Mayinger, Characteristics of transition boiling and thermal oscillation in an upflow convective boiling system, Exp. Therm. Fluid Sci. 8 (3) (1994) 195-205. https://doi.org/10.1016/0894-1777(94)90048-5
  31. S.G. Lim, H.C. No, S.W. Lee, H.G. Kim, J. Cheon, J.M. Lee, S.M. Ohk, Development of stability maps for flashing-induced instability in a passive containment cooling system for iPOWER, Nuclear Engineering and Technology 52 (1) (2020) 37-50. https://doi.org/10.1016/j.net.2019.06.026
  32. K.M. Kim, D.H. Lee, I.C. Bang, Analysis of natural circulation behaviors and flow instabilities of passive containment cooling system design for advanced PWR using MARS-KS code, Int. J. Heat Mass Tran. 147 (2020), 118982. https://doi.org/10.1016/j.ijheatmasstransfer.2019.118982
  33. Q. Wang, P. Gao, X. Chen, Z. Wang, Y. Huang, An investigation on flashing-induced natural circulation instabilities based on RELAP5 code, Ann. Nucl. Energy 121 (2018) 210-222. https://doi.org/10.1016/j.anucene.2018.07.035