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

Shen Mengsi; Lin Meng

doi:10.13832/j.jnpe.2023.02.0062

Volume 44 Issue 2

Apr. 2023

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2023 > 44(2): 62-68

Shen Mengsi, Lin Meng. Study on the Application of Interfacial Area Transport Equation in One-dimensional Two-fluid Model[J]. Nuclear Power Engineering, 2023, 44(2): 62-68. doi: 10.13832/j.jnpe.2023.02.0062

Citation:

Shen Mengsi, Lin Meng. Study on the Application of Interfacial Area Transport Equation in One-dimensional Two-fluid Model[J]. Nuclear Power Engineering, 2023, 44(2): 62-68. doi: 10.13832/j.jnpe.2023.02.0062

Citation:

PDF( 2418 KB)

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

doi: 10.13832/j.jnpe.2023.02.0062

Shen Mengsi,
Lin Meng^,

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

Received Date: 2022-05-17
Rev Recd Date: 2022-07-08
Publish Date: 2023-04-15

Abstract

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

FullText(HTML)

References(7)

References

[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.