Experimental Research on Single Phase Convection Heat Transfer in Micro-Fin Tube

FAN Guangming; SUN Zhongning; ZHU Sheng

Volume 32 Issue 1

Mar. 2025

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2011 > 32(1): 99-103

FAN Guangming, SUN Zhongning, ZHU Sheng. Experimental Research on Single Phase Convection Heat Transfer in Micro-Fin Tube[J]. Nuclear Power Engineering, 2011, 32(1): 99-103.

Citation:

FAN Guangming, SUN Zhongning, ZHU Sheng. Experimental Research on Single Phase Convection Heat Transfer in Micro-Fin Tube[J]. Nuclear Power Engineering, 2011, 32(1): 99-103.

FAN Guangming, SUN Zhongning, ZHU Sheng. Experimental Research on Single Phase Convection Heat Transfer in Micro-Fin Tube[J]. Nuclear Power Engineering, 2011, 32(1): 99-103.

Citation:

FAN Guangming, SUN Zhongning, ZHU Sheng. Experimental Research on Single Phase Convection Heat Transfer in Micro-Fin Tube[J]. Nuclear Power Engineering, 2011, 32(1): 99-103.

PDF( 291 KB)

Experimental Research on Single Phase Convection Heat Transfer in Micro-Fin Tube

College of Nuclear Science and Technology, Harbin Engineering University, Harbin, 150001, China

Received Date: 2009-11-11
Available Online: 2025-03-08

Abstract

Abstract

An experimental investigation of heat transfer and flow resistance characteristics of single phase water in three micro-fin tubes with different fin height was conducted.At the same time,the efficiency of micro-fin tubes within the experimental scope was evaluated and the optimal working region was determined.Based on the experimental data in the optimal working region,correlations for predicting the heat transfer and flow resistance were also given by multiple regression method.The result indicates that the micro-fin tubes can greatly enhance the single-phase heat transfer in turbulent flow,and the increase of heat transfer coefficient is higher than the increase of flow resistance.The accuracy of the correlation is very high,of which the deviation from the experimental value is very small.
- Micro-fin tube,
- Single-phase convection,
- Heat transfer enhancement,
- Experimental research

FullText(HTML)

References(0)

References

Relative Articles

[1]	Yang Siyuan, Yuan Bo, Wen Qinglong, Wen Shuang, Zhang Ruiqian, Yang Hongyan. Experimental Investigation for the Fretting Wear of Cr-coated Zircaloy Cladding[J]. Nuclear Power Engineering, 2024, 45(S1): 103-109. doi: 10.13832/j.jnpe.2024.S1.0103
[2]	Zhang Lin, Liu Hanzhou, Liu Xiaojing, Chen Yong, Chen Deqi. Model Study on Bubble Slide and Early-Stage Condensation Growth in Rectangular Narrow Channel[J]. Nuclear Power Engineering, 2023, 44(2): 69-76. doi: 10.13832/j.jnpe.2023.02.0069
[3]	Liu Shuai, Zhou Yuan, Kang Mingming, Yuan Yuan, Du Zhengyu, He Xiaoqiang, Hu Wei. Experimental Study on Leakage of High Temperature Sodium Heat Pipe in the Air[J]. Nuclear Power Engineering, 2023, 44(6): 39-44. doi: 10.13832/j.jnpe.2023.06.0039
[4]	He Yanqiu, Yuan Zhaofei, Zhang Yan, Tan Shushi, Zan Yuanfeng, Qiao Min, Hu Qiang. Experimental Research on Pressure Drop Characteristics of Flow Damper in Advanced Accumulator[J]. Nuclear Power Engineering, 2022, 43(2): 77-82. doi: 10.13832/j.jnpe.2022.02.0077
[5]	Liu Wei, Guo Junliang, Zhang Dan, Gui Miao, Hu Ying, Liu Yang. Experimental Study on Critical Heat Flux of Vertical Square Channel with Single Rod[J]. Nuclear Power Engineering, 2022, 43(1): 42-47. doi: 10.13832/j.jnpe.2022.01.0042
[6]	Yuan Junjie, Liu Li, Gu Hanyang. Numerical Study on Heat Transfer Enhancement of Modified Wall in U-tube Steam Generator[J]. Nuclear Power Engineering, 2022, 43(S2): 94-99. doi: 10.13832/j.jnpe.2022.S2.0094
[7]	Experiment and Numerical Study on Natural Convective Heat Transfer with Bottom Curved Heating Section Experiment and Numerical Study on Natural Convective Heat Transfer with Bottom Curved Heating Section[J]. Nuclear Power Engineering, 2020, 41(1): 199-204. doi: 10.13832/j.jnpe.2020.01.0199
[8]	Tang Simiao, Wang Chenglong, Su Guanghui, Tian Wenxi, Qiu Suizheng. Experimental Research on Heat Transfer and Thermoelectric Characteristics of Small Nuclear Power Supply Facilities[J]. Nuclear Power Engineering, 2019, 40(4): 200-202.
[9]	Li Yongliang, Huang Zhigang, Wen Yan, Zhu Haiyan, Zang Jinguang, Zeng Xiaokang, Yan Xiao, Huang Yanping, Xiao Zejun. Experimental Study on Heat Transfer of Supercritical Water in 2×2 Rod Bundles[J]. Nuclear Power Engineering, 2019, 40(5): 6-12. doi: 10.13832/j.jnpe.2019.05.0006
[10]	Deng Kuanghan, Wu Junmei, Wang Yun, Su Guanghui. Experimental Study on Effects of Nanoparticles Deposition on Flow and Heat Transfer Characteristics of Nanofluid[J]. Nuclear Power Engineering, 2017, 38(3): 164-167. doi: 10.13832/j.jnpe.2017.03.0164
[11]	Liu Liang, Zhang Yan, Xing Dianchuan, Huang Zhigang. Experimental Study on Critical Heat Flux of Rectangular Channel under Condition of Single Plate Heater[J]. Nuclear Power Engineering, 2016, 37(S2): 116-120. doi: 10.13832/j.jnpe.2016.S2.0116
[12]	Wang Minglu, Xiong Zhenqin, Gu Hanyang, YE Cheng, Cheng Xu. Heat Transfer Performance of Heat Pipe for Passive Cooling of Spent Fuel Pool[J]. Nuclear Power Engineering, 2014, 35(5): 62-65. doi: 10.13832/j.jnpe.2014.05.0062
[13]	Li Hua, Chen Ping, Qiu Suizheng, Su Guanghui, Tian Wenxi, Li Yun, Su Min. Experimental Study on Two-Phase Flow Characteristics in Pebble-Bed Porous Media Channel[J]. Nuclear Power Engineering, 2014, 35(6): 21-25. doi: 10.13832/j.jnpe.2014.06.0021
[14]	WANG Jiazhuo, YAN Changqi, DING Ming, CHEN Zheyu, SHI Shuai. Design and Research on a New Circular Plate-Shell Heat Exchanger[J]. Nuclear Power Engineering, 2014, 35(2): 141-145.
[15]	NIE Chang-hua, XU Shi-jie, LIU Xun, ZHUO Wen-bin, LI Zhang-lin, ZHENG Hua, LI Peng-zhou, YU Qing-lin. Simulation Experimental Research on Passive Residual Heat Removal Performance for Nuclear Seawater Desalination Reactor[J]. Nuclear Power Engineering, 2013, 34(6): 102-106.
[16]	LI Yong-liang, ZENG Xiao-kang, HUANG Zhi-gang, YAN Xiao, HUANG Yan-ping, XIAO Ze-jun. Experimental Study on Heat Transfer of Supercritical Water in Simple Channels[J]. Nuclear Power Engineering, 2013, 34(1): 101-107.
[17]	GONG Hou-jun, LANG Xuemei, XIE Feng. Investigation on Flow Resistance Coefficient of Wires Wrapped Tight Lattice Rods Bundle[J]. Nuclear Power Engineering, 2012, 33(S1): 45-49.
[18]	ZHANG Zhen, YAN Xiao, XIAO Ze-jun. Experimental Research on Single Phase Flow and Convection Heat Transfer in Heat-Generating Porous Media[J]. Nuclear Power Engineering, 2012, 33(S1): 1-4.
[19]	YANG Jian, YAN Xiao, CENG Min, WANG Qiuwang. Experimental Study on Forced Convective Heat Transfer in Structured Packed Porous Media with Spherical or Ellipsoidal Particles[J]. Nuclear Power Engineering, 2012, 33(S1): 85-89.
[20]	LI Yong, YAN Changqi, SUN Licheng, LIU Jia. Enhancement of Pool Boiling Heat Transfer on Porous Surface Tube[J]. Nuclear Power Engineering, 2011, 32(2): 63-67,90.