期刊文献+

蒸汽发生器实验回路倒流特性仿真分析 被引量:1

Numerical Simulation and Analysis of Reverse Flow in Steam Generator Experiment Loop
下载PDF
导出
摘要 针对立式倒U型管蒸汽发生器传热管内出现的倒流现象,基于RELAP5/MOD3.3程序,采用新的控制体划分方案对蒸汽发生器实验段进行建模,模拟实验回路中发生的倒流现象。通过与实验数据进行对比分析,验证建模方案的正确性。在此基础上,分析倒流现象对蒸汽发生器实验段流动传热的影响。结果表明:倒流现象发生在较短管内,对于单个U型管,倒流管的流量高于正流管。倒流发生后,系统进入相对稳定状态,但蒸汽发生器实验段的换热功率和进出口腔室负压降绝对值显著降低。 For the reverse flow phenomenon in the vertically inverted U-tube steam generators,a new node partition scheme was used to model the steam generator test section based on the system analysis code RELAP5/MOD3.3.The reverse flow phenomenon in the process of experiment was simulated in this paper.Compared with the experimental data,the correctness of the new scheme developed in this paper was verified.The results show that the reverse flow phenomenon occurs in the shorter U-tubes.For single U-tube,the mass flow rate of reverse flow is generally greater than that of normal flow U-tube.When the reverse flow occurs,the system will get into a relatively stable state.However,the negative pressure drop between the inlet and outlet plenums and the heat exchange of test section reduce significantly.
作者 胡高杰 于雷 郝建立 储玺 HU Gao-jie YU Lei HAO Jian-li CHU Xi(Department of Nuclear Science and Engineering, Naval University of Engineering, Wuhan 430033, Chin)
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2017年第1期67-72,共6页 Atomic Energy Science and Technology
基金 国家自然科学基金资助项目(11502298) 核反应堆系统设计技术国家重点实验室基金资助项目(HT-ZDSY-02-2015004) 核安全与仿真技术国防重点学科实验室基金资助项目(2015A041)
关键词 蒸汽发生器实验段 倒流 数值模拟 steam generator test section reverse flow numerical simulation
  • 相关文献

参考文献6

二级参考文献30

  • 1郝亚雷,于雷,蔡章生,谢海燕.核动力装置强迫循环与自然循环过渡过程特性研究[J].核科学与工程,2007,27(1):20-26. 被引量:11
  • 2杨瑞昌,覃世伟,刘若雷.自然循环蒸汽发生器倒U型管内单相水流动及传热特性分析[J].工程热物理学报,2006,27(1):130-132. 被引量:11
  • 3王飞,卓文彬,肖泽军,陈炳德.立式倒U型管蒸汽发生器倒流现象及初步分析[J].原子能科学技术,2007,41(1):65-68. 被引量:19
  • 4Sanders J. Stability of Single-Phase Natural Circulation with Inverted U-Tube Steam Generators. Journal of Heat Transfer, 1988, 110:735-742.
  • 5Kukita Y, Nakamura H, Tasaka K, et al. Nonuniform Steam Generator U-Tube Flow Distribution During Natural Circulation Tests in ROSA-IV Large Scale Test Facility. Nuclear Science and Engineering, 1988, 99:289-298.
  • 6王飞,聂常华,黄彦平,等..自然循环静态特性研究,空泡物理和自然循环重点实验室年报..,,2003..130-135..
  • 7Jeong J J, Hwang M, Lee Y J, et al. Single-and TwoPhase Flow Characteristics in the Primary Side of a UTube Steam Generator. In: The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics. Seoul, Korea, 2003.
  • 8Stumpf H, Motly F, Schultz R, et al. Reverse Primary Side Flow in Steam Generators During Natural Circulation Cooling. American Society of Mechanical Engineering, Fluid Engineering Division(FED), 1987, 61:103-109.
  • 9Yan Bing huo, Yu Lei. Theoretical Research for Natural Circulation Operational Characteristic of Ship Nuclear Machinery under Ocean Conditions [J]. Annals of Nuclear Energy, 2009, 36(6): 733-741.
  • 10LEE C H,CHANG Y H,SU S J.Investigation of PWR natural circulation at INER integral system test facility[C].[S.l.]:NURETH-6,1993:297-304.

共引文献36

同被引文献15

引证文献1

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部