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Experimental and Computational Multiphase Flow 2019, 1(1): 3-27 https://doi.org/10.1007/s42757-019-0002-5
Review Article | Open Access | Issue | Published: 05 March 2019

Thermal hydraulic considerations of nuclear reactor systems: Past, present and future challenges

Show Author's Information Guan Heng Yeoh1,2( )
School of Mechanical and Manufacturing Engineering, University of New South Wales, Sydney, NSW 2052, Australia
Australian Nuclear Science and Technology Organisation (ANSTO), Locked Bag 2001, Kirrawee DC, NSW 2232, Australia
Keywords:
nuclear reactor systems, thermal hydraulic analysis, critical heat flux
An erratum to this article is available online at https://doi.org/10.1007/s42757-020-0093-z
Cite this article:
Heng Yeoh G. Thermal hydraulic considerations of nuclear reactor systems: Past, present and future challenges. Experimental and Computational Multiphase Flow, 2019, 1(1): 3-27. https://doi.org/10.1007/s42757-019-0002-5
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Abstract Full text About this article

Thermal hydraulic analysis of nuclear reactor core and its associated systems can be performed using analysis system, subchannel or computational fluid dynamics (CFD) codes to estimate the different thermal hydraulic safety margins. The safety margins and operating power limits under different conditions of the primary as well as secondary cooling system such as the system pressure, coolant inlet temperature, coolant flow rate, and thermal power and its distributions are considered as key parameters for thermal hydraulic analysis. Considering the complexity of rod bundle geometry, boiling heat transfer and different turbulent scales bring about the many challenges in performing the thermal hydraulic analysis to ensure the safe design and operation of nuclear reactor systems under normal and abnormal conditions. A comprehensive review is presented of past, present and future challenges in state-of-the-art thermal hydraulic analysis covering various aspects of experimental, analytical and computational approaches.


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About this article

Thermal hydraulic considerations of nuclear reactor systems: Past, present and future challenges

Show Author's information Guan Heng Yeoh1,2( )
School of Mechanical and Manufacturing Engineering, University of New South Wales, Sydney, NSW 2052, Australia
Australian Nuclear Science and Technology Organisation (ANSTO), Locked Bag 2001, Kirrawee DC, NSW 2232, Australia

Abstract

Thermal hydraulic analysis of nuclear reactor core and its associated systems can be performed using analysis system, subchannel or computational fluid dynamics (CFD) codes to estimate the different thermal hydraulic safety margins. The safety margins and operating power limits under different conditions of the primary as well as secondary cooling system such as the system pressure, coolant inlet temperature, coolant flow rate, and thermal power and its distributions are considered as key parameters for thermal hydraulic analysis. Considering the complexity of rod bundle geometry, boiling heat transfer and different turbulent scales bring about the many challenges in performing the thermal hydraulic analysis to ensure the safe design and operation of nuclear reactor systems under normal and abnormal conditions. A comprehensive review is presented of past, present and future challenges in state-of-the-art thermal hydraulic analysis covering various aspects of experimental, analytical and computational approaches.

Keywords: nuclear reactor systems, thermal hydraulic analysis, critical heat flux

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Received: 23 December 2018
Revised: 31 January 2019
Accepted: 31 January 2019
Published: 05 March 2019
Issue date: March 2019

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