Sensitivity analysis using improved two-fluid model-based 1D code with the state-of-the-art constitutive equations for two-phase flow in rod bundle

Tetsuhiro Ozaki*, Takashi Hibiki, Shuichiro Miwa, Michitsugu Mori

*Corresponding author for this work

Research output: Journal Publications and ReviewsRGC 21 - Publication in refereed journalpeer-review

4 Citations (Scopus)

Abstract

In view of the importance of one-dimensional (1D) thermal-hydraulic analysis for rod bundle geometry, extensive efforts to improve constitutive equations have been made in recent years. In the present article, the state-of-the-art rod-bundle constitutive equations for flow regime map, void fraction, covariance, and interfacial area concentration models are reviewed. Among them, the constitutive relations for covariance and interfacial area concentration models may improve the conventional analysis method’s robustness. Some sensitivity analysis results using TRAC-BF1 code with the new constitutive equations are summarized and reviewed.
Original languageEnglish
Pages (from-to)350-359
JournalExperimental and Computational Multiphase Flow
Volume4
Issue number4
Online published13 Apr 2022
DOIs
Publication statusPublished - Dec 2022
Externally publishedYes

Research Keywords

  • constitutive equation
  • gas—liquid flow
  • nuclear safety analysis
  • rod bundle
  • two-fluid model

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