Research on Characteristics of Condensation Heat Transfer for Marine Nuclear Power Platform PRHR HX Under Tilting Condition

Pengzheng Li, Yongquan Li, Shaoyou Liu, Dong Zhu, Zhiqiang Zhu, Xiaming Kong
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Abstract

Passive residual heat removal heat exchanger (PRHR HX) is one of the important equipment in passive residual heat removal system (PRHRs) of marine nuclear power platform. The research on the condensation heat transfer characteristics of saturated steam in PRHR HX tube under tilting condition can provide support and optimization for passive safety system design of marine nuclear power platform. The work in this paper is of great significance to safe operation of marine nuclear power platform. The heat transfer characteristics of saturated steam condensation in the PRHR HX tube under tilting condition are analyzed by building an experimental device with a power ratio of 1:50. The experimental results show that within the range of experimental parameters in this paper, compared with the static state of the experimental device, the condensation heat transfer coefficient of saturated steam in PRHR HX tube under tilting condition is increased. When the heat flux is 190kW/m2, the heat transfer coefficient of saturated steam condensation in PRHR HX tube under tilting condition increases by about 40% compared with static condition. In this paper the formula for calculating the condensation heat transfer coefficient of saturated steam in PRHR HX tube is revised by introducing the tilt angle. The relative error between the modified formula and the experimental value is within ±10%. The research results of this paper can provide reference for the design and optimization of passive safety systems for marine nuclear power platform and similar applications.
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船用核电平台prhrhx倾斜工况下冷凝换热特性研究
被动余热排出换热器(PRHR HX)是船用核电平台被动余热排出系统的重要设备之一。研究倾斜工况下PRHR HX管内饱和蒸汽的冷凝换热特性,可为船用核电平台被动安全系统设计提供支持和优化。本文的工作对海洋核动力平台的安全运行具有重要意义。通过搭建功率比为1:50的实验装置,分析了倾斜条件下prhrhx管内饱和蒸汽冷凝的换热特性。实验结果表明,在本文实验参数范围内,与实验装置静态状态相比,倾斜状态下PRHR HX管内饱和蒸汽的冷凝换热系数增大。当热流密度为190kW/m2时,倾斜工况下PRHR HX管内饱和蒸汽冷凝换热系数较静态工况提高约40%。本文通过引入倾斜角度,对PRHR HX管内饱和蒸汽冷凝换热系数的计算公式进行了修正。修正公式与实验值的相对误差在±10%以内。本文的研究成果可为船舶核电平台及类似应用被动安全系统的设计与优化提供参考。
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