Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2014, Vol. 25 ›› Issue (5): 050601 doi: 10.13538/j.1001-8042/nst.25.050601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Steady thermal hydraulic characteristics of nuclear steam generators based on the drift flux code model

ZHANG Xiao-Ying,1 CHEN Huan-Dong,1 BAI Ning,2 ZHU Yuan-Bing, 2 REN Zhi-Hao, 2 and HUANG Kai, 2   

  1. 1School of Electric Power, South China University of Technology, Guangdong 510640, China
    2China Nuclear Power Technology Research Institute, Shenzhen 518026, China
  • Contact: HUANG Kai E-mail:huangkai@ipp.ac.cn
  • Supported by:

    Supported by the National Natural Science Foundation of China (Nos. 51376065 and 51176052)

ZHANG Xiao-Ying, CHEN Huan-Dong, BAI Ning, ZHU Yuan-Bing, REN Zhi-Hao, HUANG Kai, . Steady thermal hydraulic characteristics of nuclear steam generators based on the drift flux code model.Nuclear Science and Techniques, 2014, 25(5): 050601     doi: 10.13538/j.1001-8042/nst.25.050601

Abstract:

To investigate the steady thermal hydraulic characteristics of U-tube steam generator (SG), a 1D simulation code based on the four-equation drift flux model is developed. The U-tube channels presumably consist mainly of the primary channel, secondary channel, and tube wall. In the sub-cooling regions of the primary and secondary channels, flow is simulated using the single-phase flow model, whereas that in the boiling regions of the secondary channels is simulated using the four-equation drift flux model. The first-order equations of upwind difference are derived based on the staggered grid. Steady-state thermal hydraulic parameters are obtained with a cross-iteration scheme of heat balance and natural circulation requirement. The developed code is applied to analyze the SG behavior of the Qinshan I Nuclear Power Plant under 100%, 75%, 50%, 30%, and 15% power conditions. Analysis results are then compared with the simulation results obtained using RELAP5.

Key words: U-tube steam generator, Thermal hydraulic characteristic, Steady simulation, Four-equation drift flux model