Brayton Cycle Technology for Nuclear Power with a Focus on Compressors (www.mdpi.com)

Recent research highlights the integration of Brayton Cycle (BC) technology into nuclear power generation, showcasing its ability to significantly improve thermal efficiency and operational flexibility compared to conventional Rankine Cycle (RC) systems. This study emphasizes key working fluids like helium (He), supercritical carbon dioxide (sCO2), and nitrogen (N2), each with distinct performance characteristics. He excels at high temperatures thanks to its excellent thermal conductivity, while sCO2 offers advantages in compactness and efficiency. A crucial takeaway is the role of compressor technologies—such as axial and centrifugal designs—in optimizing BC systems under the demanding operational conditions of nuclear environments. The significance of this advancement lies in its potential to reshape the future of nuclear power. By utilizing high-temperature gas reactors and incorporating BC systems, the nuclear sector could realize enhanced efficiency and reduced physical footprint, enabling the deployment of small modular reactors (SMRs) and microreactors. However, challenges remain, including high leakage rates and material degradation under extreme conditions, necessitating robust sealing technologies and extensive testing. The findings suggest that further research on combined cycle configurations may also amplify overall efficiency in nuclear power generation, underscoring the innovative potential of Brayton Cycle systems in creating a more sustainable energy landscape.