Printed Circuit Heat Exchangers (PCHEs): A Brief Review

Authors

  • Edward Shitsi Department of Nuclear Engineering, School of Nuclear and Allied Sciences, University of Ghana, P.O. Box AE1, Kwabenya, Accra, Ghana Author https://orcid.org/0000-0002-6215-8474
  • Seth Kofi Debrah Department of Nuclear Engineering, School of Nuclear and Allied Sciences, University of Ghana, P.O. Box AE1, Kwabenya, Accra, Ghana Author
  • Vincent Yao Agbodemegbe Department of Nuclear Engineering, School of Nuclear and Allied Sciences, University of Ghana, P.O. Box AE1, Kwabenya, Accra, Ghana Author
  • Emmanuel Maurice Arthur Department of Nuclear Engineering, School of Nuclear and Allied Sciences, University of Ghana, P.O. Box AE1, Kwabenya, Accra, Ghana Author
  • Iddrisu Hamza Department of Nuclear Engineering, School of Nuclear and Allied Sciences, University of Ghana, P.O. Box AE1, Kwabenya, Accra, Ghana Author https://orcid.org/0009-0004-8904-8613
  • Esther Agyeiwaa Asomaning Department of Nuclear Engineering, School of Nuclear and Allied Sciences, University of Ghana, P.O. Box AE1, Kwabenya, Accra, Ghana Author

DOI:

https://doi.org/10.54392/irjmt2332

Keywords:

Printed Circuit Heat Exchangers, Heat Transfer Devices/Systems, Design and Optimization, Reactor Systems, Brayton and Rankine cycles

Abstract

Heat exchangers and other heat transfer devices/systems play vital roles of heat transfer in thermal fluid flow systems for industrial application. Sodium cooled fast reactors are normally designed to have two loops of sodium coolants and one loop of water coolant which generates steam for power production. The two loops of sodium coolants consist of primary cooling system of sodium which cools the fuel rods of the reactor core and secondary cooling system of sodium transferring heat from the sodium primary cooling system. The water-cooling system transfers heat from the secondary cooling system of sodium for steam generation. Lead cooled fast reactors on the other hand are designed to have primary cooling system of lead cooling the fuel rods in the reactor core and secondary cooling system of water transferring heat from the lead cooling primary system for steam generation. Water cooled Nuclear Power Plants used water to cool the reactor core in the primary system and the heat removed from the core is used for steam generation directly as in BWRs and SCWRs or in the secondary system of heat exchanger as in PWRs. Other reactor systems such as Gas-cooled fast reactor (GFR), Molten-salt reactor (MSR), High-temperature gas-cooled reactor (HTGR), and Small Modular Reactors (SMRs) also have various types of heat exchangers in their designs to support power/electricity generation. Appropriate heat exchangers are therefore needed for various stages of heat transfer in power generation systems. Thus, Heat exchangers and other heat transfer devices/systems play vital roles of heat transfer in thermal fluid flow systems for industrial applications. This study presents brief review of PCHEs which have comparable advantages over other types of heat exchangers. Recent studies on PCHEs and other heat exchanger types have been reviewed. Design and optimization of PCHEs, optimization of Brayton and Rankine circles, and fluid flow and heat transfer devices/systems have been discussed briefly. The review findings show that the design and optimization of PCHEs depends on the intended industrial application of the heat exchanger. The various channel types and channel cross-section types available for design and optimisation as well as the design and optimised system being able to withstand high pressure and temperature conditions in addition to its compact size for the intended industrial application make PCHEs unique among other types of heat exchangers.

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Published

2023-03-20

How to Cite

Shitsi, E. (2023) “Printed Circuit Heat Exchangers (PCHEs): A Brief Review”, International Research Journal of Multidisciplinary Technovation, 5(3), pp. 11–48. doi:10.54392/irjmt2332.