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Experimental and Computational Multiphase Flow 2022, 4(4): 350-359 https://doi.org/10.1007/s42757-022-0135-9
Review Article | Issue | Published: 13 April 2022

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

Show Author's Information Tetsuhiro Ozaki1( ),  Takashi Hibiki2,  Shuichiro Miwa3,  Michitsugu Mori3
TEPCO Systems, Shibusawa City Place Eitai, 2-37-28, Eitai, Koto-ku, Tokyo 135-003, Japan
School of Nuclear Engineering, Purdue University, 516 Northwestern Ave., West Lafayette, IN 47907, USA
Graduate School of Engineering, Hokkaido University, North 13, West 8, Kita-ku, Sapporo, Hokkaido 060-8628, Japan
Keywords:
two-fluid model, nuclear safety analysis, gas–liquid flow, constitutive equation, rod bundle
Cite this article:
Ozaki T, Hibiki T, Miwa S, et al. 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. Experimental and Computational Multiphase Flow, 2022, 4(4): 350-359. https://doi.org/10.1007/s42757-022-0135-9
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Abstract Full text About this article

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.


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About this article

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

Show Author's information Tetsuhiro Ozaki1( ), Takashi Hibiki2, Shuichiro Miwa3, Michitsugu Mori3
TEPCO Systems, Shibusawa City Place Eitai, 2-37-28, Eitai, Koto-ku, Tokyo 135-003, Japan
School of Nuclear Engineering, Purdue University, 516 Northwestern Ave., West Lafayette, IN 47907, USA
Graduate School of Engineering, Hokkaido University, North 13, West 8, Kita-ku, Sapporo, Hokkaido 060-8628, Japan

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.

Keywords: two-fluid model, nuclear safety analysis, gas–liquid flow, constitutive equation, rod bundle

References(21)

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Publication history
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Publication history

Received: 30 November 2020
Revised: 11 March 2021
Accepted: 11 March 2021
Published: 13 April 2022
Issue date: December 2022

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© Tsinghua University Press 2022
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