Analysis of Flow Instability for Advanced Secondary Passive Residual Heat Removal System

被引:0
|
作者
Li L. [1 ]
Su Q. [1 ]
Yan C. [1 ]
Nan Z. [1 ]
Liu H. [1 ]
Sun Z. [1 ]
Wu X. [1 ]
Lu D. [1 ]
机构
[1] China Nuclear Power Technology Research Institute, Shenzhen
关键词
Advanced secondary passive residual heat removal system; Experimental investigation; Flow instability; Influence factor; Theoretical analysis;
D O I
10.7538/yzk.2018.youxian.0755
中图分类号
学科分类号
摘要
The advanced secondary passive residual heat removal (ASP) system is one of the most important improvement measures to cope with station blackout accident in the pressurized water reator nuclear power plant. In order to obtain the operation characteristics of ASP system, the ASP system test facility (ASPTF) was constructed. The effects of different influence factors on flow instability of ASP system and theoretical analysis were obtained based on ASPTF. The experimental and theoretical results show that the flow instability of ASP system occurs in ASPTF with low system pressure and low heating power. By increasing the drag coefficient of steam pipeline or the drag coefficient of backwater pipeline, the flow instability of ASP system can be avoided. The flow instability of ASP system occurs under lower heating power conditions. The operation state of main pump influences the total inputting power of ASP system, which can further lead to the flow instability of ASP system. © 2019, Editorial Board of Atomic Energy Science and Technology. All right reserved.
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页码:1272 / 1279
页数:7
相关论文
共 16 条
  • [1] Xing J., Song D., Wu Y., HPR1000: Advanced pressurized water reactor with active and passive safety, Engineering, 2, pp. 79-87, (2016)
  • [2] Sun D.C., Li Y., Xi Z., Et al., Experimental evaluation of safety performance of emergency passive heat removal system in HPR1000, Nuclear Engineering and Design, 318, pp. 54-60, (2017)
  • [3] Lu X., Zhang J., Luo H., Et al., Study on startup response of secondary passive residual heat removal system in 1000 MWe PWR nuclear power plant, Atomic Energy Science and Technology, 48, pp. 457-462, (2014)
  • [4] Li L., Fu X., Wen Q., Et al., Experimental and numerical investigation of natural circulation characteristics of multi-coupled systems, Nuclear Science and Engineering, 38, 3, pp. 403-410, (2018)
  • [5] Liang W., Xie H., Analyses on flow instability of secondary-side passive residual heat removal system for advanced nuclear heating reactor, Nuclear Power Engineering, 39, 2, pp. 14-19, (2018)
  • [6] Zhang Y., Tian W., Qiu S., Et al., Analyses on flow instability of passive residual heat removal system for CPR1000, Nuclear Power Engineering, 32, 6, pp. 38-41, (2011)
  • [7] Zhou L., Xi Z., Xiong W., Et al., Analysis of influncer for secondary-side passive residual heat removal system based on RELAP5 code, Nuclear Power Engineering, 33, 6, pp. 72-76, (2012)
  • [8] Xu H., Wu X., Lu D., Et al., Test study on heat transfer capability of advanced secondary passive residual heat removal system, Atomic Energy Science and Technology, 52, 3, pp. 447-452, (2018)
  • [9] Reyes J.N., Hochreiter L., Scaling analysis for the OSU AP600 test facility (APEX), Nuclear Engineering and Design, 186, pp. 53-109, (1998)
  • [10] Chen L., Chang H., Li Y., Et al., Analysis on working pressure selection of ACME integral test facility, Atomic Energy Science and Technology, 45, 10, pp. 1215-1220, (2011)