Nuclear Engineering and Technology

  • 제53권2호
  • /
  • Pages.446-454
  • /
  • 2021
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지
DOI QR코드

DOI QR Code

Program development and preliminary CHF characteristics analysis for natural circulation loop under moving condition

  • Gui, Minyang (School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Tian, Wenxi (School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Wu, Di (School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Chen, Ronghua (School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Su, G.H. (School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Qiu, Suizheng (School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University)
  • 투고 : 2020.02.17
  • 심사 : 2020.07.18
  • 발행 : 2021.02.25
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

Critical heat flux (CHF) has traditionally been evaluated using look-up tables or empirical correlations for nuclear power plants. However, under complex moving condition, it is necessary to reconsider the CHF characteristics since the conventional CHF prediction methods would no longer be applicable. In this paper, the additional forces caused by motions have been added to the annular film dryout (AFD) mechanistic model to investigate the effect of moving condition on CHF. Moreover, a theoretical model of the natural circulation loop with additional forces is established to reflect the natural circulation characteristics of the loop system. By coupling the system loop with the AFD mechanistic model, a CHF prediction program called NACOM for natural circulation loop under moving condition is developed. The effects of three operating conditions, namely stationary, inclination and rolling, on the CHF of the loop are then analyzed. It can be clearly seen that the moving condition has an adverse effect on the CHF in the natural circulation system. For the calculation parameters in this paper, the CHF can be reduced by 25% compared with the static value, which indicates that it is important to consider the effects of moving condition to retain adequate safety margin in subsequent thermal-hydraulic designs.

키워드

과제정보

The authors appreciate the support from Natural Science Foundation of China (Grant No. 11622541) and National Key R&D Program of China (Grant No. 2017YFE0302100).

참고문헌

  1. K. Lee, M. Kim, J.I. Lee, P. Lee, Recent advances in Ocean Nuclear power plants, Energies 8 (10) (2015) 11470-11492. https://doi.org/10.3390/en81011470
  2. Y.K. Panov, V.I. Polunichev, K.V. Zverev, Nuclear floating power desalination complexes, in: Proceedings of Four Technical Meeting, International Atomic Energy Agency, Vienna, IAEA-TECDOC. 1056, 1998, pp. 93-104.
  3. R. Martinek, Akademik Lomonosov. Preparations for premiere in full swing, Atw. Internationale Zeitschrift fuer Kernenergie 63 (8-9) (2018) 437-439.
  4. A. Kurosawa, Y. Fujiie, Two phase flow behavior induced by ship's motion, J. Nucl. Sci. Technol. 4 (11) (1967) 584-586. https://doi.org/10.1080/18811248.1967.9732811
  5. G. Yun, S.Z. Qiu, G.H. Su, D.N. Jia, The influence of ocean conditions on two-phase flow instability in a parallel multi-channel system, Ann. Nucl. Energy 35 (9) (2008) 1598-1605. https://doi.org/10.1016/j.anucene.2008.03.003
  6. T. Si-chao, G.H. Su, G. Puzhen, Heat transfer model of single-phase natural circulation flow under a rolling motion condition, Nucl. Eng. Des. 239 (10) (2009) 2212-2216. https://doi.org/10.1016/j.nucengdes.2009.05.002
  7. J. Hao, W. Chen, Z. Chen, The development of natural circulation operation support program for ship nuclear power machinery, Ann. Nucl. Energy (2012) 199-205.
  8. H. Murata, I. Iyori, M. Kobayashi, Natural circulation characteristics of a marine reactor in rolling motion, Nucl. Eng. Des. 118 (2) (1990) 141-154. https://doi.org/10.1016/0029-5493(90)90053-Z
  9. J.H. Kim, T.W. Kim, S.M. Lee, G.C. Park, Study on the natural circulation characteristics of the integral type reactor for vertical and inclined conditions, Nucl. Eng. Des. 207 (1) (2001) 21-31. https://doi.org/10.1016/S0029-5493(00)00417-9
  10. S. Tan, G.H. Su, P. Gao, Experimental and theoretical study on single-phase natural circulation flow and heat transfer under rolling motion condition, Appl. Therm. Eng. 29 (14) (2009) 3160-3168. https://doi.org/10.1016/j.applthermaleng.2009.04.019
  11. B. Yan, L. Yu, Y. Li, Research on operational characteristics of passive residual heat removal system under rolling motion, Nucl. Eng. Des. 239 (11) (2009) 2302-2310. https://doi.org/10.1016/j.nucengdes.2009.06.026
  12. T. Ishida, Development of Analysis Code for Thermal Hydro-Dynamics of Marine Reactor under Multi-Dimensional Ship Motions, Retran-02/grav (No. JAERI-M-91-226), Japan Atomic Energy Research Inst, Tokyo, 1992.
  13. H.J. Kim, G.C. Park, Development of RETRAN-03/MOV code for thermal-hydraulic analysis of nuclear reactor under moving conditions, J. Korean Nucl. Soc. 28 (6) (1996) 542-550.
  14. J.H. Kim, T.W. Kim, S.M. Lee, G.C. Park, Study on the natural circulation characteristics of the integral type reactor for vertical and inclined conditions, Nucl. Eng. Des. 207 (1) (2001) 21-31. https://doi.org/10.1016/S0029-5493(00)00417-9
  15. C. Tan, H. Zhang, H. Zhao, Development of ocean-condition code based on RELAP5, Nucl. Power Eng. 30 (6) (2009) 53-56.
  16. B.H. Yan, L. Yu, The development and validation of a thermal hydraulic code in rolling motion, Ann. Nucl. Energy 38 (8) (2011) 1728-1736. https://doi.org/10.1016/j.anucene.2011.04.007
  17. L. He, B. Wang, G. Xia, M. Peng, Study on natural circulation characteristics of an IPWR under inclined and rolling condition, Nucl. Eng. Des. 317 (2017) 81-89. https://doi.org/10.1016/j.nucengdes.2017.03.033
  18. P.B. Whalley, P. Hutchinson, G.F. Hewitt, The Calculation of Critical Heat Flux in Forced Convection Boiling, 7520, AERE, Altamonte Springs, 1973, pp. 1317-1342.
  19. T.E.D.C.M. Saito, E.D. Hughes, M.W. Carbon, Multi-fluid modeling of annular two-phase flow, Nucl. Eng. Des. 50 (2) (1978) 225-271. https://doi.org/10.1016/0029-5493(78)90041-9
  20. T. Okawa, A. Kotani, I. Kataoka, M. Naito, Prediction of critical heat flux in annular flow using a film flow model, J. Nucl. Sci. Technol. 40 (6) (2003) 388-396. https://doi.org/10.3327/jnst.40.388
  21. D.X. Du, W.X. Tian, G.H. Su, S.Z. Qiu, Y.P. Huang, X. Yan, Theoretical study on the characteristics of critical heat flux in vertical narrow rectangular channels, Appl. Therm. Eng. 36 (1) (2012) 21-31. https://doi.org/10.1016/j.applthermaleng.2011.11.039
  22. M. Gui, W. Tian, D. Wu, et al., Development of a three-field mechanistic model for dryout prediction in annular flow, Ann. Nucl. Energy (2019), https://doi.org/10.1016/j.anucene.2019.106978.
  23. Y. Katto, H. Ohno, An improved version of the generalized correlation of critical heat flux for the forced convective boiling in uniformly heated vertical tubes, Int. J. Heat Mass Tran. 27 (9) (1984) 1641-1648. https://doi.org/10.1016/0017-9310(84)90276-X
  24. H. Umekawa, M. Ozawa, N. Ishida, Dryout and post-dryout heat transfer in a natural circulation loop of liquid nitrogen, Heat Tran. Jpn. Res. 26 (7) (1997) 449-458. Co-sponsored by the Society of Chemical Engineers of Japan and the Heat Transfer Division of ASME. https://doi.org/10.1002/(SICI)1520-6556(1997)26:7<449::AID-HTJ3>3.0.CO;2-W
  25. I. Kataoka, M. Ishii, A. Nakayama, Entrainment and desposition rates of droplets in annular two-phase flow, Int. J. Heat Mass Tran. 43 (9) (2000) 1573-1589. https://doi.org/10.1016/S0017-9310(99)00236-7
  26. T. Okawa, T. Kitahara, K. Yoshida, et al., New entrainment rate correlation in annular two-phase flow applicable to wide range of flow condition, Int. J. Heat Mass Tran. 45 (1) (2002) 87-98. https://doi.org/10.1016/S0017-9310(01)00111-9
  27. V. Jain, A.K. Nayak, P.K. Vijayan, D. Saha, R.K. Sinha, Experimental investigation on the flow instability behavior of a multi-channel boiling natural circulation loop at low-pressures, Exp. Therm. Fluid Sci. 34 (6) (2010) 776-787. https://doi.org/10.1016/j.expthermflusci.2010.01.007
  28. D.W. Zhao, G.H. Su, Z.H. Liang, Y.J. Zhang, W.X. Tian, S.Z. Qiu, Experimental research on transient critical heat flux in vertical tube under oscillatory flow condition, Int. J. Multiphas. Flow 37 (9) (2011) 1235-1244. https://doi.org/10.1016/j.ijmultiphaseflow.2011.06.012
  29. M. Gui, W. Tian, D. Wu, G.H. Su, S. Qiu, Study on CHF characteristics in narrow rectangular channel under complex motion condition, Appl. Therm. Eng. 166 (2019) 114629.