A review on the thermal-hydraulic performance and optimization of printed circuit heat exchangers for supercritical CO2 in advanced nuclear power systems

Abstract Printed circuit heat exchangers (PCHEs) are a widely considered candidate for heat exchangers in the supercritical CO2 Brayton cycle, which have been proposed to be used in advanced nuclear power systems. The current article presents an overview of the research status of the heat transfer and pressure drop of PCHEs with different channel types in the supercritical CO2 Brayton cycle. The industrial feasibility and the maturity level of PCHEs with different channel types were discussed in detail. Some discussions and suggestions on the further research of PCHEs were presented. The literature review indicated that very few theoretical analyses and experiments on thermal-hydraulic performance of PCHEs have been carried out. Most studies focused on the effects of channel structure and operating parameters on the heat transfer and pressure drop of PCHEs. Limited attention has been paid to the industrial feasibility and maturity level of PCHEs with different channel types, which could be important limitations for the large-scale application of PCHEs. Based on the comprehensive consideration of the thermal-hydraulic performance, pressure resistance, maturity level and manufacturing cost, the zigzag channel with a semicircular cross-section is the preferred channel type for the supercritical CO2 side of PCHEs.