Experimental Investigation on Pressure Oscillation of Submerged Steam Jet Condensation with Non-condensable Gas

被引：0
|
作者：
Liu J. [1 ]
Liu X. [1 ]
Sun Z. [1 ]
Meng Z. [1 ]
机构：
[1] Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin
来源：
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2019年 / 53卷 / 02期
关键词：
Condensation; Non-condensable gas; Pressure oscillation; Submerged steam jet;
D O I：
10.7538/yzk.2018.youxian.0407
中图分类号：
学科分类号：
摘要：
Experimental investigation on the effect of non-condensable gas content, temperature and steam mass velocity on submerged steam jet condensation pressure oscillation was performed. Experimental conditions across condensation oscillation (CO) region and stable condensation (SC) region. Experimental results show that for pure steam jets, the pressure oscillation dominant frequency decreases with the rise of water temperature, while the pressure oscillation intensity increases with the rise of water temperature. Both pressure oscillation dominant frequency and intensity increase with steam mass velocity in CO region. However, the pressure oscillation dominant frequency decreases with the rise of steam mass velocity, and the pressure oscillation intensity hardly changes with the rise of steam mass velocity in SC region. For air-steam mixture gas jets, the pressure oscillation dominant frequency decreases with the rise of air mass fraction. However as the air mass fraction increases, the pressure oscillation intensity rapidly decreases at first, then slowly increases. Both pressure oscillation dominant frequency and intensity reach a minimum when the air mass fraction is between 0.05 and 0.1. © 2019, Editorial Board of Atomic Energy Science and Technology. All right reserved.
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页码：312 / 318
页数：6
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共 22 条
  • [1] Park C.K., Song C.H., Influence of key parameters on the APR1400 in-containment refueling water storage tank hydrodynamic loads, Journal of Nuclear Science & Technology, 40, 10, pp. 820-826, (2003)
  • [2] Lim J., Choi S.W., Yang J., Et al., Assessment of passive safety system performance under main steam line break accident, Annals of Nuclear Energy, 64, pp. 287-294, (2014)
  • [3] Miller F.P., Vandome A.F., Mcbrewster J., Et al., GE Hitachi Nuclear Energy, (2011)
  • [4] Cho S., Song C.H., Park C.K., Et al., Experimental study on dynamic pressure pulse in direct contact condensation of steam jets discharging into subcooled water, Proceedings of NTHAS98, (1998)
  • [5] Su T.M., Suppression-pool temperature limits for BWR containments, NUREG-0783, (1981)
  • [6] Giencke E., Pressure distribution due to a steam bubble collapse in a BWR pressure suppression pool, Nuclear Engineering and Design, 65, 2, pp. 175-196, (1979)
  • [7] Chan C.K., Lee C.K.B., A regime map for direct contact condensation, International Journal of Multiphase Flow, 8, 1, pp. 11-20, (1982)
  • [8] Youn D.H., Ko K.B., Lee Y.Y., Et al., The direct contact condensation of steam in a pool at low mass flux, Journal of Nuclear Science and Technology, 40, 10, pp. 881-885, (2003)
  • [9] Simpson M.E., Chan C.K., Hydrodynamics of a subsonic vapor jet in subcooled liquid, Journal of Heat Transfer, 104, 2, pp. 271-278, (1981)
  • [10] Fukuda S., Pressure variation due to vapor condensation in liquid, Ⅱ: Phenomena at large vapor mass flow rate, Journal of Atomic Energy Society of Japan, 24, pp. 466-474, (1982)
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