Study on Fluid-Thermal-Structural Coupling of Helical Tube Once-Through Steam Generator

Jiao Meng; Zhao Xinwen; Fu Shengwei; Jiang Jiahang; Ouyang Kehan

doi:10.13832/j.jnpe.2024.040027

Volume 46 Issue 3

Jun. 2025

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Article Navigation > Nuclear Power Engineering > 2025 > 46(3): 213-219

Jiao Meng, Zhao Xinwen, Fu Shengwei, Jiang Jiahang, Ouyang Kehan. Study on Fluid-Thermal-Structural Coupling of Helical Tube Once-Through Steam Generator[J]. Nuclear Power Engineering, 2025, 46(3): 213-219. doi: 10.13832/j.jnpe.2024.040027

Citation:

Jiao Meng, Zhao Xinwen, Fu Shengwei, Jiang Jiahang, Ouyang Kehan. Study on Fluid-Thermal-Structural Coupling of Helical Tube Once-Through Steam Generator[J]. Nuclear Power Engineering, 2025, 46(3): 213-219. doi: 10.13832/j.jnpe.2024.040027

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Study on Fluid-Thermal-Structural Coupling of Helical Tube Once-Through Steam Generator

doi: 10.13832/j.jnpe.2024.040027

1.
College of Nuclear Science and Technology, Naval University of Engineering, Wuhan, 430033, China
2.
Naval Staff, Beijing, 100071, China

Received Date: 2024-04-21
Rev Recd Date: 2024-08-22

Available Online: 2025-06-09

Publish Date: 2025-06-09

Abstract

Abstract

The double-sided heat exchange structure of the helical tube once-through steam generator (OTSG) effectively enhances heat transfer and has been applied in integrated reactors. The phenomenon of tube dryout in helical tube OTSG leads to a temperature jump, potentially causing damage to the tubes. This paper establishes a fluid-thermal-structural coupling analysis model of the single-channel helical tube OTSG, analyzes the void fraction and temperature distribution on the secondary side wall of the tubes, and further investigates the stress field of helical tube OTSG. The results indicate that the void fraction and temperature on the secondary side tube wall exhibit a spiral banded distribution. The temperature continuously jumps due to the banded distribution of dryout on the outer wall of the helical tube along the z direction, resulting in a corresponding jump in the equivalent stress of the tube wall. The fluctuation amplitude of the equivalent stress increases with the magnitude of the temperature jump. The stress in the dryout banded region of the tube exhibits concentration, with the maximum stress fluctuation reaching around 11 MPa. The stress distribution in the circumferential banded region also varies, with the stress fluctuation exceeding 10 MPa in the helical tube and 7 MPa in the straight tube.
- Helical tube once-through steam generator (OTSG),
- Fluid-thermal-structural coupling,
- Temperature jump,
- Stress fluctuation

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References(12)

References

[1]	余航,赵新文,傅晟威. 船用核动力装置止回阀的流固热耦合研究[J]. 核动力工程,2019, 40(4): 25-28.
[2]	焦猛,蔡琦,张永发,等. 基于运行数据的船用堆波动管热分层现象研究[J]. 核动力工程,2021, 42(5): 200-205.
[3]	许雷雷,梁国兴. 承压热冲击下压力容器断裂力学分析[J]. 原子能科学技术,2014, 48(11): 2078-2084.
[4]	SHEHURNE P A, HORNBACH, MCILREE A. Residual stress in otsg tube expansion transitions[J]. Materials Science, 1997, 38(3): 345-351.
[5]	RAHIMI M, OWEN I, MISTRY J. Thermal stresses in boiler tubes arising from high-speed cleaning jets[J]. International Journal of Mechanical Sciences, 2003, 45(6-7): 995-1009. doi: 10.1016/j.ijmecsci.2003.09.007
[6]	陈玲,王鑫铭,张永发,等. 直流蒸汽发生器蒸干点波动引起的热应力及疲劳分析[J]. 核动力工程,2023, 44(4): 23-25.
[7]	LESHNOFF S D, ERDOGAN F. Mechanical integrity analysis of TMI-1 OTSG unplugged tubes[J]. Nuclear Engineering and Design, 1984, 79(1): 31-37. doi: 10.1016/0029-5493(84)90186-9
[8]	KWON J S, KIM D H, SHIN S G. Assessment of thermal fatigue induced by dryout front oscillation in printed circuit steam generator[J]. Nuclear Engineering and Technology, 2022, 54(3): 1085-1097. doi: 10.1016/j.net.2021.09.004
[9]	KANG H O, SEO J K, KIM Y W, et al. Structural integrity confirmation of a once-through steam generator from the viewpoint of flow instability[J]. Journal of Nuclear Science and Technology, 2007, 44(1): 64-72. doi: 10.1080/18811248.2007.9711257
[10]	ÖZCEYHAN V. Conjugate heat transfer and thermal stress analysis of wire coil inserted tubes that are heated externally with uniform heat flux[J]. Energy Conversion and Management, 2005, 46(9-10): 1543-1559. doi: 10.1016/j.enconman.2004.08.003
[11]	ZHONG X P, YU J Y, YAN S Y, et al. Analysis of wall temperature jump of China Generation IV SFR Steam Generator[J]. Annals of Nuclear Energy, 2018, 114: 510-517. doi: 10.1016/j.anucene.2017.12.059
[12]	JIAO M, ZHAO X W, FU S W, et al. Numerical analysis of coupled flow and heat transfer in primary and secondary sides of double-side heating once-through steam generator with helical tubes[J]. Numerical Heat Transfer, Part A: Applications, 2023(10): 1-16.