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A Review of the Research and Development of Brayton Cycle Technology in Nuclear Power Applications with a Focus on Compressor Technology

Aidan Rigby, Logan Williams, Václav Novotný, Tyler Westover, Rami Saeed and Junyung Kim ()
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Aidan Rigby: Idaho National Laboratory, Idaho Falls, ID 83415, USA
Logan Williams: Idaho National Laboratory, Idaho Falls, ID 83415, USA
Václav Novotný: Idaho National Laboratory, Idaho Falls, ID 83415, USA
Tyler Westover: Idaho National Laboratory, Idaho Falls, ID 83415, USA
Rami Saeed: Idaho National Laboratory, Idaho Falls, ID 83415, USA
Junyung Kim: Idaho National Laboratory, Idaho Falls, ID 83415, USA

Energies, 2025, vol. 18, issue 22, 1-25

Abstract: This study reviews the integration of Brayton Cycle (BC) systems in nuclear power generation, emphasizing their potential to enhance thermal efficiency and operational flexibility over traditional Rankine Cycle (RC) systems. Key working fluids, such as helium (He), supercritical carbon dioxide (sCO 2 ), nitrogen (N 2 ), and air, are evaluated for their performance, efficiency, and compatibility with nuclear systems. He is recognized for its high thermal conductivity and inertness at elevated temperatures, while sCO 2 demonstrates advantages in compactness and efficiency in midrange temperatures. This article also highlights the importance of compressor designs in optimizing BC performance and reviews, available compressor technologies. Axial and centrifugal compressor designs enable efficient gas compression while managing the thermal and mechanical stresses associated with high-pressure operations in nuclear systems. Combined with variable geometry components and advanced materials, these technologies address the challenges posed by varying load conditions. Despite the promising features of BC systems, several challenges persist, including high leakage rates and material degradation under extreme conditions, which necessitate robust sealing technologies and thorough testing. The insights gained from operational experiences at facilities, such as the Oberhausen II plant and the High-Temperature He Test Facility (HHV), underscore the complexities involved in designing high-temperature gas turbines for nuclear applications. This review concludes that as the nuclear industry evolves, BC systems hold significant promise for contributing to a sustainable energy future, particularly in the context of small modular reactors (SMRs) and microreactors. Further exploration of combined cycle configurations that combine BCs with RCs may enhance overall efficiency and flexibility in power generation.

Keywords: nuclear power; Brayton Cycle; compressor technology; working fluids (search for similar items in EconPapers)
JEL-codes: Q Q0 Q4 Q40 Q41 Q42 Q43 Q47 Q48 Q49 (search for similar items in EconPapers)
Date: 2025
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