PLIF Technology and Its Application in Researches of Nuclear Reactor Thermal-hydraulics
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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。
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关键词:
- 平面激光诱导荧光（PLIF） /
- 热工水力 /
- 浓度场 /
- 温度场 /
- 两相分布
Abstract: The Nuclear Reactor Engineering Laboratory of Harbin Engineering University (HEU-NUREL) has long been committed to the exploration of planar laser-induced fluorescence (PLIF) technology and its application in reactor thermal hydraulic study. As a non-invasive advanced measurement method, PLIF technology can achieve qualitative and quantitative measurements of the full-plane of the physical field, providing benchmark experimental data for numerical model validation. This paper will comprehensively display the latest achievements and progress of HEU-NUREL in thermal hydraulic research of nuclear reactors based on PLIF technology, focus on the practical path and measurement effect of PLIF technology in concentration measurement, temperature field analysis, two-phase distribution, and technical exploration, and describe the the technical features and unique contributions of PLIF technology in different fields of thermal and hydraulic study, aiming to promote PLIF technology to better serve the reactor system design and safety analysis. -
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
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