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

Tan Sichao; Wei Tianyi; Yu Xiaoyong; Xie Guanhui; Li Xupeng; Tian Ruifeng

doi:10.13832/j.jnpe.2024.01.0001

Volume 45 Issue 1

Feb. 2024

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2024 > 45(1): 1-10

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

Citation:

PDF( 77956 KB)

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

doi: 10.13832/j.jnpe.2024.01.0001

Tan Sichao^{1, 2
,},
Wei Tianyi^{1, 2
,},
Yu Xiaoyong^{1, 2
,},
Xie Guanhui^{1, 2},
Li Xupeng^{1, 2},
Tian Ruifeng^{1, 2}

1.
Heilongjiang Provincial Key Laboratory of Nuclear Power System and Equipment, Harbin Engineering University, Harbin, 150001, China
2.
Key Laboratory of Nuclear Safety and Advanced Nuclear Energy Technology, Ministry of Industry and Information Technology, Harbin Engineering University, Harbin, 150001, China

Received Date: 2023-06-24
Rev Recd Date: 2023-07-08
Publish Date: 2024-02-15

Abstract

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.
- Planar laser-induced fluorescence (PLIF),
- Thermal-hydraulics,
- Concentration field,
- Temperature field,
- Two-phase distribution

FullText(HTML)

References(27)

References

[1]	CHANG A Y, BATTLES B E, HANSON R K. Simultaneous measurements of velocity, temperature, and pressure using rapid cw wavelength-modulation laser-induced fluorescence of OH[J]. Optics Letters, 1990, 15(12): 706-708. doi: 10.1364/OL.15.000706
[2]	VAN CRUYNINGEN I, LOZANO A, HANSON R K. Quantitative imaging of concentration by planar laser-induced fluorescence[J]. Experiments in Fluids, 1990, 10(1): 41-49. doi: 10.1007/BF00187871
[3]	黄真理,李玉梁,余常昭. PLIF技术测量浓度场及其二维数字校正[J]. 力学学报,1994, 26(5): 616-624.
[4]	米争鹏. 基于激光诊断技术的棒束内温度分布特性研究[D]. 哈尔滨: 哈尔滨工程大学,2018.
[5]	QI P Y, LI X, LI X, et al. Experimental study on the resistance characteristics of the rod bundle channel with spacer grid under low-frequency pulsating flows[J]. Annals of Nuclear Energy, 2019, 131: 80-92. doi: 10.1016/j.anucene.2019.03.027
[6]	LI X, MI Z P, TAN S C, et al. PIV study of velocity distribution and turbulence statistics in a rod bundle[J]. Annals of Nuclear Energy, 2018, 117: 305-317. doi: 10.1016/j.anucene.2018.03.036
[7]	WANG X Y, WANG R Q, TAN S J, et al. Flow visualization and mixing quantification in a rod bundle using laser induced fluorescence[J]. Nuclear Engineering and Design, 2016, 305: 1-8. doi: 10.1016/j.nucengdes.2016.01.007
[8]	LI X, MI Z P, TAN S C, et al. Experimental investigation of fluid mixing inside a rod bundle using laser induced fluorescence[J]. Progress in Nuclear Energy, 2019, 110: 90-102. doi: 10.1016/j.pnucene.2018.09.012
[9]	黄云龙,谭思超,米争鹏,等. 激光诱导荧光技术对棒束通道内定位格架搅浑特性研究[J]. 原子能科学技术,2018, 52(5): 839-846. doi: 10.7538/yzk.2017.youxian.0586
[10]	ZHANG Q, SU J K, DU W A, et al. Experimental study on mixing phenomenon inside reactor down-comer under single-loop injection using laser induced fluorescence[J]. Progress in Nuclear Energy, 2019, 117: 103046. doi: 10.1016/j.pnucene.2019.103046
[11]	张琦,谭思超,刘宇生,等. 平面激光诱导荧光法硼浓度分布特性研究[J]. 哈尔滨工程大学学报,2018, 39(5): 876-880.
[12]	赵婷杰. 基于激光诊断技术下降段硼浓度分布特性研究[D]. 哈尔滨: 哈尔滨工程大学,2017.
[13]	ALA A A, TAN S C, ELTAYEB A, et al. Experimental study on sudden contraction and split into the inlets of two parallel rectangular jets[J]. Experimental Thermal and Fluid Science, 2019, 104: 272-283. doi: 10.1016/j.expthermflusci.2019.03.002
[14]	CHEN M P, XIE G H, LI D Y, et al. Mixing characteristic measurement of flow in reactor pressure vessel by laser induced fluorescent method[C]//2021 28th International Conference on Nuclear Engineering. Virtual, Online: ASME, 2021.
[15]	XIE G H, CHEN M C, LI D Y, et al. Flow mixing characteristics in double loop reactor pressure vessel under accident conditions[C]//The 29th International Conference on Nuclear Engineering. Virtual, Online: ASME, 2022.
[16]	米争鹏,谭思超,李兴,等. 棒束通道温度场可视化实验研究[C]//第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会论文集. 荣成: 中国核学会核能动力分会反应堆热工流体专业委员会,2017: 673-680.
[17]	米争鹏,谭思超,李兴,等. 棒束通道温度场可视化实验研究[J]. 原子能科学技术,2018, 52(5): 847-854. doi: 10.7538/yzk.2018.52.05.0847
[18]	米争鹏,谭思超,邹思远,等. 棒束通道内温度场分布特性研究[J]. 原子能科学技术,2020, 54(9): 1644-1651. doi: 10.7538/yzk.2019.youxian.0599
[19]	王啸宇. 基于激光诊断技术的棒束间流动交混特性研究[D]. 哈尔滨: 哈尔滨工程大学,2016.
[20]	赵婷杰,谭思超,王啸宇,等. 双色激光诱导荧光法在矩形通道温度场测量中的应用[C]//第十四届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2015年度学术年会论文集. 北京: 国核学会核能动力分会反应堆热工流体专业委员会,2015: 297-301.
[21]	WEI T Y, CHEN J R, ZHANG B, et al. Effects of ocean conditions on water level measurement of pressurizer[J]. Annals of Nuclear Energy, 2022, 169: 108913. doi: 10.1016/j.anucene.2021.108913
[22]	WANG B, CHEN B W, TIAN R F. Review of research progress on flow and rupture characteristics of liquid film on corrugated plate wall[J]. Annals of Nuclear Energy, 2019, 132: 741-751. doi: 10.1016/j.anucene.2019.06.060
[23]	毛峰,田瑞峰,陈怡炫. 波形板干燥器内壁面液膜破裂临界条件的实验研究[J]. 原子能科学技术,2018, 52(5): 855-861. doi: 10.7538/yzk.2018.52.05.0855
[24]	WANG B, KE B Z, CHEN B W, et al. Study on the size of secondary droplets generated owing to rupture of liquid film on corrugated plate wall[J]. International Journal of Heat and Mass Transfer, 2020, 147: 118904. doi: 10.1016/j.ijheatmasstransfer.2019.118904
[25]	祁沛垚,邓坚,谭思超,等. 基于PIV技术的低雷诺数下棒束通道流场研究[J]. 核动力工程,2021, 42(1): 18-22. doi: 10.13832/j.jnpe.2021.01.0018
[26]	YU X Y, ZHANG Y H, LI S W, et al. Simultaneous measurement of the structures of the velocity and thermal boundary layers in the rod bundle channel[J]. International Journal of Heat and Mass Transfer, 2022, 192: 122906. doi: 10.1016/j.ijheatmasstransfer.2022.122906
[27]	YUAN D D, DENG J, ZHU J H, et al. Simultaneous temperature field investigations of blockage accidents in a narrow rectangular channel by experiments and simulations[J]. Annals of Nuclear Energy, 2022, 171: 109007. doi: 10.1016/j.anucene.2022.109007