Study on Fluid-Thermal-Structural Coupling of Helical Tube Once-Through Steam Generator
-
摘要: 螺旋套管式直流蒸汽发生器(OTSG)的双面换热结构能有效增强换热,在一体化反应堆中得到应用,螺旋套管式OTSG管道内蒸干现象导致温度跃升,可能导致管道损伤。本文建立了单通道下螺旋套管式OTSG的流-热-力耦合计算模型,分析了管道二次侧壁面出现的含气率和温度分布,并进一步分析了螺旋套管式OTSG的应力场。结果表明,OTSG的二次侧管道壁面上含气率和温度呈螺旋条带分布,沿z方向螺旋套管外壁蒸干的条带分布导致温度不断跳跃,导致管壁的等效应力同样波动,等效应力的波动幅度随着温度跳跃的幅度增大而增大,管道在蒸干条带区存在应力集中,应力的波动幅度最大在11 MPa左右。周向上蒸干条带区的应力分布同样存在周向不均匀,螺旋管应力波动幅度达到10 MPa以上,直管应力波动幅度为7 MPa。
-
关键词:
- 螺旋套管式直流蒸汽发生器(OTSG) /
- 流-热-力耦合 /
- 温度跃升 /
- 应力波动
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. -
表 1 流-热-力耦合边界条件
Table 1. Fluid-Thermal-Structural Coupling Boundary Conditions
边界名称 约束/载荷 直管内壁面 0.2P 直管外壁面 P 螺旋管内壁面 P 螺旋管外壁面 0.2P 螺旋管上端面 固定约束 螺旋管下端面 自由 直管上端面 固定约束 直管下端面 x、y方向约束 P—压力。 表 2 边界条件
Table 2. Boundary Conditions
流体区域/材料特性 位置 参数名 参数值 螺旋管内一次侧 入口 流速V/( m·s−1) 温度T/K 出口 压力P/MPa 直管外一次侧 入口 流速V/( m·s−1) 温度T/K 出口 压力P/MPa 外壁面 热流密度/( W·m−2) −81158.0 环隙内二次侧 入口 流速 0.0473V 温度 0.602T 出口 压力 0.2P 回流温度 0.897T TA16合金 密度/( kg·m−3) 4650 比热容/( J·kg−1·K−1) 580 热导率/( W·m−1·K−1) 9.36 -
[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. -