Review of Experimental and Numerical Studies on Critical Heat Flux in China

Yun Guo () and Yijun Zhang
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Yun Guo: School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026, China
Yijun Zhang: School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026, China

Energies, 2025, vol. 18, issue 4, 1-23

Abstract: This article presents an exhaustive and comprehensive review of research endeavors conducted in China over the past three decades focusing on critical heat flux—a thermal–hydraulic phenomenon of paramount importance in nuclear engineering. CHF represents the ultimate threshold of heat transfer capability, governed by fundamental physical principles, and serves as a cornerstone in the design of reactor cores, fundamentally delineating the reactor’s capacity for safe heat dissipation. In this study, we undertake a meticulous analysis of 60+ research papers published in Chinese by a diverse array of Chinese research institutions spanning the last three decades, encompassing both experimental and numerical simulation investigations. The experimental research is systematically reviewed. The experimental setups and test sections are examined in detail. Then, the experimental parameters and conclusions are analyzed comprehensively. This examination elucidates the achievements attained and the challenges encountered in the experimental domain. In the realm of numerical simulation research, this review consolidates the prevailing hypotheses regarding inherent mechanisms, modeling methodologies, and their validations against experimental data. Building upon the existing research accomplishments and acknowledging the emerging trends in fluid mechanics research, particularly the integration of next-generation measurement technologies and artificial intelligence, a strategic and forward-looking research trajectory is proposed. This trajectory aims to guide and inspire future endeavors in this crucial and intricate field, fostering a deeper understanding and enhanced performance of nuclear reactors through innovative and rigorous research.

Keywords: critical heat flux; thermal–hydraulic; China (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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