Published July 2019 | Version v1
Journal article

Numerical research on thermal mixing characteristics in a 45-degree T-junction for two-phase stratified flow during the emergency core cooling safety injection

  • 1. State Key Laboratory of Multiphase Flow in Power Engineering, School of Nuclear Science and Technology, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi'an Jiaotong University, Xi'an 710049 (China)
  • 2. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610041 (China)

Description

Highlights: • Thermal mixing with direct contact condensation was investigated using STARCCM+. • The temperature distributions were validated by the experimental measurement. • A fitting correlation was summarized according to simulation results. -- Abstract: The thermal mixing and direct contact condensation are the most significant phenomena appeared during the Emergency Core Cooling (ECC) system safety injection process. The three-dimensional thermal mixing characteristics accompanied by complicated direct contact condensation are investigated using CFD method. Firstly, the feasibility of two-phase CFD models are validated by the experimental data obtained from the XJTU-ECC experimental apparatus. Results show that the established CFD models could predict the two-phase mixing process correctly and the errors between numerical results and experimental data are smaller than 30%. Then the two-phase thermal mixing features, including temperature fields, velocity fields and volume fraction, are achieved in detail. Moreover, the local steam condensation characteristics are studied carefully and results show that the condensation rate is proved closely related to the coolant thermodynamic ratio between the main pipe and branch pipe. Finally, an empirical correlation is proposed to predict the condensation rate in case that the thermodynamic ratio is lower than 0.55. This work provides a fundamental guideline for the ECC system structure optimization and fatigue aging in the advanced nuclear power plants.

Additional details

Identifiers

DOI
10.1016/j.pnucene.2019.03.009;
PII
S0149197019300666;

Publishing Information

Journal Title
Progress in Nuclear Energy
Journal Volume
114
Journal Page Range
p. 91-104
ISSN
0149-1970
CODEN
PNENDE

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Copyright
Copyright (c) 2019 Elsevier Ltd. All rights reserved.