Nuclear Engineering and Technology

  • 제52권9호
  • /
  • Pages.1955-1962
  • /
  • 2020
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지
DOI QR코드

DOI QR Code

Experimental and numerical investigations on effect of reverse flow on transient from forced circulation to natural circulation

  • Li, Mingrui (College of Nuclear Science and Technology, Naval University of Engineering) ;
  • Chen, Wenzhen (College of Nuclear Science and Technology, Naval University of Engineering) ;
  • Hao, Jianli (College of Nuclear Science and Technology, Naval University of Engineering) ;
  • Li, Weitong (College of Nuclear Science and Technology, Naval University of Engineering)
  • 투고 : 2019.10.28
  • 심사 : 2020.02.27
  • 발행 : 2020.09.25
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

In a sudden shutdown of primary pump or coolant loss accident in a marine nuclear power plant, the primary flow decreases rapidly in a transition process from forced circulation (FC) to natural circulation (NC), and the lower flow enters the steam generator (SG) causing reverse flow in the U-tube. This can significantly compromise the safety of nuclear power plants. Based on the marine natural circulation steam generator (NCSG), an experimental loop is constructed to study the characteristics of reverse flow under middle-temperature and middle-pressure conditions. The transition from FC to NC is simulated experimentally, and the characteristics of SG reverse flow are studied. On this basis, the experimental loop is numerically modeled using RELAP5/MOD3.3 code for system analysis, and the accuracy of the model is verified according to the experimental data. The influence of the flow variation rate on the reverse flow phenomenon and flow distribution is investigated. The experimental and numerical results show that in comparison with the case of adjusting the mass flow discontinuously, the number of reverse flow tubes increases significantly during the transition from FC to NC, and the reverse flow has a more severe impact on the operating characteristics of the SG. With the increase of flow variation rate, the reverse flow is less likely to occur. The mass flow in the reverse flow U-tubes increases at first and then decreases. When the system is approximately stable, the reverse flow is slightly lower than obverse flow in the same U-tube, while the flow in the obverse flow U-tube increases.

키워드

참고문헌

  1. B.L. Smith, Computational Fluid Dynamics for Natural Circulation Flows, 2005, pp. 535-551. IAEA:AEA-TECDOC-1281. Vienna.
  2. Y. Kukita, H. Nakamura, K. Tasaka, Nonuniform steam generator U-tube flow distribution during natural circulation tests in ROSA-IV Large Scale Test Facility, Nucl. Sci. Eng. 99 (1988) 289-298. https://doi.org/10.13182/NSE99-289
  3. J. Sanders, Stability of single-phase natural circulation with inverted U-tube steam generators, J. Heat. Transf. 110 (1988) 735-742. https://doi.org/10.1115/1.3250553
  4. J.J. Jeong, M. Hwang, Y.J. Lee, B.D. Chung, Non-uniform flow distribution in the steam generator U-tubes of a pressurized water reactor plant during single and two-phase natural circulations, Nucl. Eng. Des. 231 (2004) 303-314. https://doi.org/10.1016/j.nucengdes.2004.02.002
  5. J.L. Hao, W.Z. Chen, D. Zhang, S.M. Wang, Scaling modeling analysis of flow instability in U-tubes of steam generator under natural circulation, Ann. Nucl. Energy 64 (2014) 169-175. https://doi.org/10.1016/j.anucene.2013.10.001
  6. X. Chu, W.Z. Chen, J.L. Hao, D. Zhang, Experimental and theoretical investigations on effect of U-tube inlet and secondary temperatures on reverse flow inside UTSG, Prog. Nucl. Energy 110 (2017) 1073-1080. https://doi.org/10.1016/j.anucene.2017.08.040
  7. B. Yang, C. Wang, X.J. Li, Analysis of single phase flow instability in U-tubes of steam generator, Ann. Nucl. Energy 109 (2017) 180-184. https://doi.org/10.1016/j.anucene.2017.05.028
  8. M. Hirano, Y. Sudo, Analytical study on thermal-hydraulic behavior of transient from forced circulation to natural circulation in JRR-3, J. Nucl. Sci. Technol. 23 (4) (1985) 352-368. https://doi.org/10.1080/18811248.1986.9734992
  9. H. Hoffmann, K. Marten, D. Weinberg, H. Kamide, Thermohydraulic model experiments on the transition from forced to natural circulation for pool-type fast reactors, Nucl. Technol. 99 (1992) 374-385. https://doi.org/10.13182/NT92-A34721
  10. G.L. Xia, G.H. Su, M.J. Peng, Analysis of natural circulation operational characteristics for integrated pressurized water reactor, Ann. Nucl. Energy 92 (2016) 304-311. https://doi.org/10.1016/j.anucene.2016.01.032
  11. F.A. Braz Filho, G.B. Ribeiro, A.D. Caldeira, Fourier analysis of the RELAP5/3D adaptive time-stepping scheme on a natural circulation loop, Ann. Nucl. Energy 113 (2018) 65-74. https://doi.org/10.1016/j.anucene.2017.11.018
  12. M. Younas Alia, G.W. Wu, S.Y. Liu, M. Jin, J. Wang, Research of coupled wall conduction effects on forced and natural circulation of LBE in CLEAR-S, Prog. Nucl. Energy 111 (2019) 74-84. https://doi.org/10.1016/j.pnucene.2018.10.009
  13. W.B. Liu, L. Wang, T. Zhou, G.Y. Zhang, Y.Q. Bai, Transient characteristics analysis of lead-based reactor from forced circulation to natural circulation, Prog. Nucl. Energy 117 (2019) 103052. https://doi.org/10.1016/j.pnucene.2019.103052
  14. Rosa-V Group. ROSA-V large scale test facility (LSTF) system description for the third and fourth simulated fuel assemblies. In: Japan Atomic Energy Agency, JAERITech 2003-037.
  15. F.J. Moody, Introduction to Unsteady Thermo-Fluid Mechanics, John Wiley and Sons, 1990.
  16. W.Z. Chen, L.M. Zhang, H.G. Xiao, Principles of Nuclear Reactor Engineering, Chinese Atomic Energy Press, Beijing, 2019.
  17. W.Z. Chen, L. Yu, J.L. Hao, Thermal Hydraulics of Nuclear Power Plants, Chinese Atomic Energy Press, Beijing, 2013.
  18. M.R. Li, J.L. Hao, W.Z. Chen, W.T. Li, Experimental and theoretical investigations on reverse flow characteristics in vertically inverted U-tube steam generator under transient condition, Prog. Nucl. Energy 120 (2020) 103216, https://doi.org/10.1016/j.pnucene.2019.103216.

피인용 문헌

  1. Single-phase density wave oscillation -A new phenomenon of flow instability in inverted U-Type Steam Generator vol.143, 2020, https://doi.org/10.1016/j.pnucene.2021.104030