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非能动余热排出换热器流量分配及瞬态热分层特性数值模拟研究

何少鹏 王明军 田文喜 秋穗正 苏光辉

原子能科学技术2025,Vol.59Issue(5):1006-1015,10.
原子能科学技术2025,Vol.59Issue(5):1006-1015,10.DOI:10.7538/yzk.2024.youxian.0669

非能动余热排出换热器流量分配及瞬态热分层特性数值模拟研究

Numerical Simulation of Flow Distribution and Transient Thermal Stratifica-tion Characteristics of Passive Residual Heat Removal Heat Exchangers

何少鹏 1王明军 1田文喜 1秋穗正 1苏光辉1

作者信息

  • 1. 西安交通大学动力工程多相流国家重点实验室,陕西 西安 710049||西安交通大学核反应堆热工水力研究室,陕西 西安 710049
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摘要

Abstract

The passive residual heat removal heat exchanger(PRHR HX)is a key component of the third-generation advanced pressurized water reactor(PWR)nuclear power plant's passive safety systems.The PRHR HX has numerous heat transfer tubes with varying lengths and arrangements on the primary side,leading to different flow distributions and resistance characteristics.The secondary side experiences various physical processes,including natural convection,mixed convection,and boiling heat transfer,significantly impacting the heat exchanger's natural circulation and residual heat removal capacity.Current numerical analysis methods for PRHR HX inadequately consider flow distribution and resistance characteristics on the primary side.A porous medium-pipe-level coupling calculation method was established,introducing a parallel C-shaped pipe-level flow distribution and resistance iterative solution model.A matching strategy for grid control volumes on both sides and physical field communication was proposed,and a mathematical-physical model suitable for natural circulation and two-phase boiling conditions was developed for the PRHR HX,enabling coupling analysis between the primary side's pipe-level resolution physical field and the secondary side's porous medium computational domain.Based on data from Japan's ROSA test facility,program validation was conducted,comparing heat transfer amounts,primary side outlet temperatures,and temperature profiles under single-phase and two-phase conditions,with good agreement between calculated and experimental values.Flow distribution and resistance characteristics on the primary side under coupled conditions of the AP1000 reactor's PRHR HX was explored.The variation of secondary side thermal stratification with different operational parameters was analyzed.Results indicate that when the total flow rate on the primary side increases,the proportion of frictional pressure drop in the total pressure drop increases,diminishing the gravitational pressure drop's dominant role in flow distribution,leading to flow distribution unevenness reduce.Additionally,heat transfer at the upper section increases,enhancing natural convection,resulting in faster thermal stratification on the secondary side,though with a lower Strouhal number peak.When the primary side inlet temperature rises,heat transfer intensifies on both sides,increasing the density difference at the inlet and outlet of the heat transfer tubes,thereby enhancing the gravitational pressure drop's role in flow distribution unevenness.Consequently,flow distribution unevenness increases,with significant increasing in upper section heat transfer and faster thermal stratification formation,while natural convection does not significantly enhance,resulting in a higher Strouhal number peak.When the secondary side's initial temperature rises,heat transfer decreases on both sides,reducing the density difference at the inlet and outlet of the heat transfer tubes,weakening the gravitational pressure drop's dominant influence on flow distribution unevenness,though the impact is relatively small.Additionally,the theoretical maximum temperature gradient decreases,slightly weakening the lower section heat transfer and natural convection mixing effects,leading to faster thermal stratification formation with a higher Strouhal number peak.This study can provide a reference for the numerical simulation analysis and optimization design of PRHR HX.

关键词

非能动余热排出换热器/流量分配/热分层/数值模拟

Key words

PRHR HX/flow distribution/thermal stratification/numerical simulation

分类

核科学

引用本文复制引用

何少鹏,王明军,田文喜,秋穗正,苏光辉..非能动余热排出换热器流量分配及瞬态热分层特性数值模拟研究[J].原子能科学技术,2025,59(5):1006-1015,10.

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