相界面浓度输运方程在一维两流体模型中的应用研究

沈梦思; 林萌

doi:10.13832/j.jnpe.2023.02.0062

相界面浓度输运方程在一维两流体模型中的应用研究

doi: 10.13832/j.jnpe.2023.02.0062

沈梦思,
林萌^,

上海交通大学核科学与工程学院，上海，201100

基金项目: 国家自然科学基金（U21B2059）

详细信息

作者简介:
沈梦思（1990—），男，博士研究生，现主要从事两相流动数值模拟相关研究，E-mail: shenmengsi1234@163.com

通讯作者:
林　萌，linmeng@sjtu.edu.cn

中图分类号: TL333
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- 被引次数: 0
出版历程
- 收稿日期: 2022-05-17
- 修回日期: 2022-07-08
- 刊出日期: 2023-04-15

Study on the Application of Interfacial Area Transport Equation in One-dimensional Two-fluid Model

Shen Mengsi,
Lin Meng^,

School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai, 201100, China

摘要

摘要: 为解决一维两流体模型核电厂系统分析程序中使用流型图所带来的缺陷，提高系统分析程序计算的准确性，探索在一维两流体模型中应用相界面浓度输运方程（IATE）对两相流动进行预测。采用FORTRAN语言开发耦合了IATE的一维两流体模型求解器（Solver-IATE），并对其进行验证。基于Solver-IATE对小直径绝热圆管内向上泡状流进行了数值模拟，并与采用流型图的计算结果进行了对比。研究结果表明：采用IATE计算的相界面浓度结果比采用流型图的计算结果更接近实验值。因此，在一维两流体模型中使用IATE可以提高其计算相界面浓度的准确性，进而提高一维两流体模型核电厂系统分析程序计算两相间相互作用项的准确性，能更准确预测反应堆的瞬态响应特性。
- 相界面浓度输运方程（IATE） /
- 一维两流体模型 /
- 耦合 /
- 数值模拟
Abstract: In order to resolve the drawbacks of flow regime map used in the one-dimensional two-fluid model based nuclear power plant system analysis code and improve the accuracy of the system analysis code, this paper explores the application of the interfacial area transport equation (IATE) in the one-dimensional two-fluid model to predict the two-phase flow. The one-dimensional two-fluid model solver coupled with IATE (Solver-IATE) is developed and verified with FORTRAN. The numerical simulation of upward bubbly flow in the small adiabatic circular tube is conducted based on Solver-IATE, and the results are compared with the simulational results from the flow regime map. The study shows that the phase interfacial area concentration results calculated using IATE are closer to the experimental value than that using the flow regime map. Thus, the application of IATE in the one-dimensional two-fluid model can improve the accuracy of the calculation of phase interfacial area concentration, thereby improving the accuracy of one-dimensional two-fluid model based nuclear power plant system analysis code in calculating interaction terms between two phases and more accurately predicting the transient response characteristics of reactor.
- Interfacial area transport equation (IATE) /
- One-dimensional two-fluid model /
- Coupling /
- Numerical simulation

HTML全文

图 1 run 3空泡份额计算与对比

Figure 1. Calculation and Comparison of Void Faction for run 3　　　　　　

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图 2 run 3相界面浓度计算与对比

Figure 2. Calculation and Comparison of Interfacial Area Concentration for run 3

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图 3 run 3气泡索特直径计算与对比

Figure 3. Calculation and Comparison of Bubble Sauter Diameter for run 3

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图 4 run 11相界面浓度计算与对比

Figure 4. Calculation and Comparison of Interfacial Area Concentration for run 11

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图 5 run 11气泡索特直径计算与对比

Figure 5. Calculation and Comparison of Bubble Sauter Diameter for run 11

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图 6 run 11 IATE源项强度

$ {\varPhi _{\text{P}}} $—压力变化导致的相界面浓度变化率，(m·s)⁻¹；$ {\varPhi _{{\text{conv}}}} $—对流引起的相界面浓度变化率，(m·s)⁻¹

Figure 6. Source Term Strength of IATE for run 11

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图 7 run 1相界面浓度计算与对比

Figure 7. Calculation and Comparison of Interfacial Area Concentration for run 1

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图 8 run 1气泡索特直径计算与对比

Figure 8. Calculation and Comparison of Bubble Sauter Diameter for run 1

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图 9 run 12相界面浓度计算与对比

Figure 9. Calculation and Comparison of Interfacial Area Concentration for run 12

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图 10 run 12气泡索特直径计算与对比

Figure 10. Calculation and Comparison of Bubble Sauter Diameter for run 12

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图 11 run 12 IATE源项强度

Figure 11. Source Term Strength of IATE for run 12

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图 12 run 1压强计算与对比

Figure 12. Calculation and Comparison of Pressure Intensity for run 1

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图 13 run 1气相速度计算与对比

Figure 13. Calculation and Comparison of Gas Phase Velocity for run 1

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图 14 run 1液相速度计算与对比

Figure 14. Calculation and Comparison of Liquid Phase Velocity for run 1

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表 1 T. Hibiki和M.Ishii的实验工况

Table 1. Experimantal Conditions of T. Hibiki and M. Ishii

实验工况	j_g/(m·s⁻¹)	j_l/(m·s⁻¹)	$ \left\langle {{\alpha _{\text{g}}}} \right\rangle $	是否充分发展
run 1	0.055	0.262	0.12	是
run 2	0.078	0.262	0.17	是
run 3	0.041	0.872	0.04	是
run 4	0.081	0.872	0.08	是
run 5	0.143	0.872	0.14	是
run 6	0.046	1.750	0.03	是
run 7	0.116	1.750	0.06	是
run 8	0.257	1.750	0.13	是
run 9	0.575	1.750	0.22	否
run 10	0.051	3.490	0.02	是
run 11	0.201	3.490	0.06	否
run 12	0.702	3.490	0.50	否
j_g—表观气相流速；j_l—表观液相流速

下载: 导出CSV

参考文献(7)

[1]	ISHII M, KOCAMUSTAFAOGULLARI G. Two-phase-flow models and their limitations: DE83009007[R]. Milwaukee, USA: Argonne National Lab., 1982.
[2]	KIM S, ISHII M, KONG R, et al. Progress in two-phase flow modeling: interfacial area transport[J]. Nuclear Engineering and Design, 2021, 373: 111019. doi: 10.1016/j.nucengdes.2020.111019
[3]	TALLEY J D. Interfacial area transport equation for vertical and horizontal bubbly flows and its application to the TRACE code [D]. State College: The Pennsylvania State Univ., 2012.
[4]	何辉. 运动条件下的环状流界面输运机制及模型[D]. 重庆: 重庆大学, 2016.
[5]	Nuclear Regulatory Commission. RELAP5/MOD3 code manual: user’s guide and input requirements. Volume 2: NUREG/CR-5535, INEL-95/0174[R]. Washington: Nuclear Regulatory Commission, 1995.
[6]	ISHII M, KIM S, UHLE J. Interfacial area transport equation: model development and benchmark experiments[J]. International Journal of Heat and Mass Transfer, 2002, 45(15): 3111-3123. doi: 10.1016/S0017-9310(02)00041-8
[7]	BAJOREK S, GAVRILAS M, GINGRICH C, et al. TRACE V5.0 theory manual, field equations, solution methods, and physical models: ML120060218[R]. Washington: Nuclear Regulatory Commission, 2008.