Effect of heat transfer tube leak on dynamic characteristic of steam generator

被引:0
作者
Sun, Bao-Zhi [1 ]
Shi, Jian-Xin [1 ]
Lei, Yu [2 ]
Li, Na [1 ]
Zheng, Lu-Song [1 ]
Liu, Shang-Hua [1 ]
机构
[1] College of Power and Energy Engineering, Harbin Engineering University, Harbin
[2] Harbin Power System Engineering and Research Institute Co., Ltd., Harbin
来源
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2015年 / 49卷 / 04期
关键词
Drift flow model; Heat transfer tube leak; Steam generator; Thermal-hydraulic characteristic;
D O I
10.7538/yzk.2015.49.04.0680
中图分类号
学科分类号
摘要
Taking the steam generator of Daya Bay Nuclear Power Station as the research object, one-dimensional dynamic model of the steam generator based on drift flux theory and leak model of heat transfer tube were established. Steady simulation of steam generator under different conditions was carried out. Based on verifying the drift flux model and leak model of heat transfer tube, the effect of leak location and flow rate under different conditions on steam generator's key parameters was studied. The results show that the drift flux model and leak model can reflect the law of key parameter change accurately such as vapor mass fraction and steam pressure under different leak cases. The variation of the parameters is most apparent when the leak is at the entrance of boiling section and vapor mass fraction varies from 0.261to 0.163when leakage accounts for 5% of coolant flow rate. The successful prediction of the effect of heat transfer tube leak on dynamic characteristics of the steam generator based on drift flux theory supplies some references for monitoring and taking precautionary measures to prevent heat transfer tube leak accident. ©, 2015, Atomic Energy Press. All right reserved.
引用
收藏
页码:680 / 687
页数:7
相关论文
共 10 条
  • [1] Ji H.J., Young C.K., The effect of tube rupture location on the consequences of multiple steam generator tube rupture event, Annals of Nuclear Energy, 29, pp. 1809-1826, (2002)
  • [2] Ferng Y.M., Investigating the distribution characteristics of boiling flow and released nuclide in the steam generator secondary side using CFD methodology, Annals of Nuclear Energy, 34, pp. 724-731, (2007)
  • [3] Del LOpez P.C., Velasco F.J.S., Herranz L.E., Simulation of a gas jet entering the secondary side of a steam generator during a SGTR sequence: Validation of a FLUENT6.2model, Nuclear Engineering and Design, 240, pp. 2206-2214, (2010)
  • [4] Jiang L., Peng M., Liu J., Et al., Effects of rupture location and the number of ruptured tubes on the analysis of SGTR accident, Nuclear Science and Engineering, 32, 1, pp. 44-49, (2012)
  • [5] Xiong J., Dynamic modeling and simulation of a nuclear steam generator, Chinese Journal of Nuclear Science and Engineering, 9, 1, pp. 20-33, (1989)
  • [6] Yang C., Tang S., He Z., Development of U-tube steam generator model and its simulation, Journal of System Simulation, 11, 3, pp. 169-171, (1999)
  • [7] Guo W., Dynamic simulation of U-tube steam generator by using drift-flux model, Chinese Journal of Nuclear Science and Engineering, 20, 1, pp. 64-69, (2000)
  • [8] Herbert S.W., Dynamic modeling of vertical U-tube steam generators for operational safety systems, (1982)
  • [9] Bao J., Sun B., Zhang G., Simulation and analysis of steam generator water level based on nonlinear level model, IEEE-APPEEC, pp. 1-3, (2012)
  • [10] Ding X., Operation principle and parameters of natural circulation steam generator, Nuclear Power Station, 2, 3, pp. 15-21, (2003)