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PLIF技术及其在反应堆热工水力研究中的应用

谭思超 魏天一 于晓勇 谢冠辉 李旭鹏 田瑞峰

谭思超, 魏天一, 于晓勇, 谢冠辉, 李旭鹏, 田瑞峰. PLIF技术及其在反应堆热工水力研究中的应用[J]. 核动力工程, 2024, 45(1): 1-10. doi: 10.13832/j.jnpe.2024.01.0001
引用本文: 谭思超, 魏天一, 于晓勇, 谢冠辉, 李旭鹏, 田瑞峰. PLIF技术及其在反应堆热工水力研究中的应用[J]. 核动力工程, 2024, 45(1): 1-10. doi: 10.13832/j.jnpe.2024.01.0001
Tan Sichao, Wei Tianyi, Yu Xiaoyong, Xie Guanhui, Li Xupeng, Tian Ruifeng. PLIF Technology and Its Application in Researches of Nuclear Reactor Thermal-hydraulics[J]. Nuclear Power Engineering, 2024, 45(1): 1-10. doi: 10.13832/j.jnpe.2024.01.0001
Citation: Tan Sichao, Wei Tianyi, Yu Xiaoyong, Xie Guanhui, Li Xupeng, Tian Ruifeng. PLIF Technology and Its Application in Researches of Nuclear Reactor Thermal-hydraulics[J]. Nuclear Power Engineering, 2024, 45(1): 1-10. doi: 10.13832/j.jnpe.2024.01.0001

PLIF技术及其在反应堆热工水力研究中的应用

doi: 10.13832/j.jnpe.2024.01.0001
基金项目: 国家自然科学基金(12275059);中核集团领创科研项目
详细信息
    作者简介:

    谭思超(1979—),男,教授,博士研究生导师,主要从事反应堆热工水力方面的研究,E-mail: tansichao@hrbeu.edu.cn

  • 中图分类号: TL33

PLIF Technology and Its Application in Researches of Nuclear Reactor Thermal-hydraulics

  • 摘要: 哈尔滨工程大学核反应堆工程研究团队(HEU-NUREL)长期致力于平面激光诱导荧光(PLIF)技术的探索及其在反应堆热工水力研究中的应用。PLIF技术作为非侵入式先进测量手段,可实现物理场全平面的定性和定量测量,为数值模型验证提供基准实验数据。本文全面展示HEU-NUREL基于PLIF技术在核反应堆热工水力研究等方面的最新成果和进展,重点介绍应用PLIF技术在浓度测量、温度场分析、两相分布及技术探索等方面的实践路径和测量效果,阐述PLIF技术及相关方法在热工水力不同领域的技术特点和独特贡献,旨在促进PLIF技术更好地服务反应堆系统设计与安全分析。

     

  • 图  1  定位格架下游不同高度处瞬时浓度分布云图[7]

    Figure  1.  Instantaneous Concentration Distribution at Different Heights Downstream of the Spacer Grid

    图  2  定位格架下游不同高度处横截面时均浓度分布云图[8]

    Figure  2.  Time-averaged Concentration Distribution in Cross Section at Different Heights Downstream of the Spacer Grid

    图  3  纵截面时均浓度分布云图[9]

    Figure  3.  Time-averaged Concentration Distribution in Longitudinal Section

    图  4  不同高度环形下降段横截面浓度分布[12]

    T—时间

    Figure  4.  Concentration Distribution in Cross Section of Annular Downcomer at Different Heights

    图  5  下降段纵截面浓度分布时序图[12]

    Figure  5.  Concentration Distribution Time Sequence in Longitudinal Section of Downcomer

    图  6  压力容器内非均匀硼稀释实验系统

    Figure  6.  Experimental System for Non-uniform Boron Dilution in Pressure Vessel

    图  7  压力容器纵截面浓度场演化[14]

    Figure  7.  Concentration Field Evolution in Longitudinal Section of Pressure Vessel

    图  8  堆芯横截面浓度场演化[15]

    Figure  8.  Concentration Field Evolution in Cross Section of Reactor Core

    图  9  棒束通道温度场实验系统示意图

    Figure  9.  Schematic Diagram of Temperature Field Experimental System of Rod Bundle Channel

    图  10  不同流量下定位格架下游0~5Dh温度分布[18]

    Figure  10.  Temperature Distribution of 0~5Dh Downstream of the Spacer Grid under Different Flows

    图  11  定位格架下游不同高度处热边界层分布

    Figure  11.  Thermal Boundary Layer Distribution at Different Heights Downstream of the Spacer Grid

    图  12  不同加热功率条件下温度场的分布[20]

    Figure  12.  Temperature Field Distribution under Different Heating Power Conditions

    图  13  冷热流体交混时温度云图

    Figure  13.  Temperature Cloud Map during Mixing of Cold and Hot Fluids

    图  14  晃荡条件下稳压器液面位置变化[21]

    Figure  14.  Free Surface Variation in Pressurizer under Sloshing

    图  15  波形板汽水分离可视化研究[23]

    Figure  15.  Visualization Study on Steam Water Separation of Corrugated Plate Walls

    图  16  棒束通道多参数场同步测量系统

    Figure  16.  Multiparameter Field Synchronous Measurement System of Rod Bundle Channel

    图  17  不同实验工况下速度边界层及热边界层分布[26]

    Figure  17.  Distribution of Velocity Boundary Layer and Thermal Boundary Layer under Different Conditions

    图  18  阻塞工况下归一化速度场和温度场分布[27]

    Figure  18.  Normalized Velocity and Temperature Field Distribution under Blocking Conditions

    图  19  测量结果对比

    Figure  19.  Comparison of Measurement Results

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出版历程
  • 收稿日期:  2023-06-24
  • 修回日期:  2023-07-08
  • 刊出日期:  2024-02-15

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