Research on Correction Method of Pressure Spike at Gas-Liquid Interface Crossing Cells Based on RELAP5

Wang Xiaohu; Zhao Pinghui; Ye Taohong; Xiong Yan; Tan Chao; Chen Yunlong

doi:10.13832/j.jnpe.2024.01.0034

Volume 45 Issue 1

Feb. 2024

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2024 > 45(1): 34-40

Wang Xiaohu, Zhao Pinghui, Ye Taohong, Xiong Yan, Tan Chao, Chen Yunlong. Research on Correction Method of Pressure Spike at Gas-Liquid Interface Crossing Cells Based on RELAP5[J]. Nuclear Power Engineering, 2024, 45(1): 34-40. doi: 10.13832/j.jnpe.2024.01.0034

Citation:

Wang Xiaohu, Zhao Pinghui, Ye Taohong, Xiong Yan, Tan Chao, Chen Yunlong. Research on Correction Method of Pressure Spike at Gas-Liquid Interface Crossing Cells Based on RELAP5[J]. Nuclear Power Engineering, 2024, 45(1): 34-40. doi: 10.13832/j.jnpe.2024.01.0034

Citation:

Wang Xiaohu, Zhao Pinghui, Ye Taohong, Xiong Yan, Tan Chao, Chen Yunlong. Research on Correction Method of Pressure Spike at Gas-Liquid Interface Crossing Cells Based on RELAP5[J]. Nuclear Power Engineering, 2024, 45(1): 34-40. doi: 10.13832/j.jnpe.2024.01.0034

PDF( 13062 KB)

Research on Correction Method of Pressure Spike at Gas-Liquid Interface Crossing Cells Based on RELAP5

doi: 10.13832/j.jnpe.2024.01.0034

1.
School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, 230026, China
2.
Institute of Plasma, Hefei Institute of Physical Science, Chinese Academy of Science, Hefei, 230026, China
3.
School of Engineering Science, University of Science and Technology of China, Hefei, 230026, China
4.
China Nuclear Power Operation Technology Corporation Ltd., Wuhan, 430074, China

Received Date: 2023-04-17
Rev Recd Date: 2023-06-05
Publish Date: 2024-02-15

Abstract

Abstract

In order to reduce or eliminate the non-physical pressure spike of gas-liquid interface crossing cell edges in vertical stratified flow calculation of RELAP5 and to improve the stability of the calculation, this study investigates the causes of pressure spikes in the vertical stratified flow from the perspective of momentum equations, and proposes a method to reduce the pressure spikes by directly correcting the momentum equations. It is found that the liquid phase unsteady term is the main cause of such pressure spikes. Based on this, a numerical method for correcting the liquid phase unsteady term is developed and validated with a vertical pipe filling and discharging problem and a manometer problem. The validation results show that the correction method can achieve the effect of reducing the non-physical pressure spikes in the process of the gas-water interface crossing cell edges, and therefore, it is beneficial to improve the stability of the code calculation.
- Vertical stratified flow,
- Gas-liquid interface,
- RELAP5,
- Pressure spikes,
- Momentum equations

FullText(HTML)

References(15)

References

[1]	CO L I T. RELAP5/MOD3 code manual. Volume 4, models and correlations: NUREG/CR-5535[R]. Washington: US Nuclear Regulatory Commission, 1995.
[2]	WEAVER W L. Improvements to mixture level tracking model: INEL-96/00097[R]. Idaho Falls: Idaho National Lab, 1996.
[3]	巢飞,单建强,张勇,等. 两流体双压力模型半隐数值算法研究[J]. 核动力工程,2018, 39(2): 142-148. doi: 10.13832/j.jnpe.2018.01.0142
[4]	ARAI M. Characteristics and stability analyses for two-phase flow equation systems with viscous terms[J]. Nuclear Science and Engineering, 1980, 74(2): 77-83. doi: 10.13182/NSE80-A19624
[5]	LYCZKOWSKI R W, GIDASPOW D, SOLBRIG C W, et al. Characteristics and stability analyses of transient one-dimensional two-phase flow equations and their finite difference approximations[J]. Nuclear Science and Engineering, 1978, 66(3): 378-396. doi: 10.13182/NSE78-4
[6]	HALEY T C, DREW D A, LAHEY JR R T. An analysis of the eigenvalues of bubbly two-phase flows[J]. Chemical Engineering Communications, 1991, 106(1): 93-117. doi: 10.1080/00986449108911538
[7]	RAMSHAW J D, TRAPP J A. Characteristics, stability, and short-wavelength phenomena in two-phase flow equation systems[J]. Nuclear Science and Engineering, 1978, 66(1): 93-102. doi: 10.13182/NSE78-A15191
[8]	ZOU L, ZHAO H H, ZHANG H B, et al. A revisit to the hicks' hyperbolic two-pressure two-phase flow model[C]//17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17). Xi’an, 2017.
[9]	ABE Y, AKIMOTO H, KAMO H, et al. Elimination of numerical pressure spikes induced by two-fluid model[J]. Journal of Nuclear Science and Technology, 1993, 30(12): 1214-1224. doi: 10.1080/18811248.1993.9734615
[10]	ADACHI H. Multi-dimensional thermal-hydraulics in pressure vessel during reflood phase of a PWR-LOCA[J]. Ceskoslovenská Pediatrie, 1989, 45(6): 335-8.
[11]	AKIMOTO H, IGUCHI T, OKABE K, et al. Evaluation report on CCTF core-II reflood test C2-6, run 64; Effect of radial power profile[R]. Tokai-mura: Japan Atomic Energy Research Institute, 1985.
[12]	CO L I T. RELAP5/MOD3 code manual: code structure, system models, and solution methods. Volume 1: NUREG/CR-5535[R]. Washington: US Nuclear Regulatory Commission, 1995.
[13]	AKTAS B, MAHAFFY J H. A two-phase level tracking method[J]. Nuclear Engineering and Design, 1996, 162(2-3): 271-280. doi: 10.1016/0029-5493(95)01132-3
[14]	RANSOM V H. Course A---numerical modeling of two-phase flows for presentation at Ecole d'Ete d'Analyse Numerique: EGG-EAST-8546; CONF-8906249-1[R]. Idaho Falls: EG and G Idaho, 1989.
[15]	MOODY F J, WINTERBONE D E. Introduction to unsteady thermofluid mechanics[J]. International Journal of Heat and Fluid Flow, 1991, 12(4): 384.