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Natural convection analysis in a safety pool of an SMR using three-dimensional component-scale thermal hydraulics technique
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DOI：10.1007/s12206-026-0234-9.png)
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Abstract
En 中文
In this study, component-scale simulations were performed to analyze natural convection in the reactor's passive safety cooling pool. Conventional one-dimensional system-scale thermal-hydraulic codes widely used in the nuclear field are limited in capturing cross-flow or swirling flow, thus making them inadequate for analyzing natural convection phenomena in reactor cooling pools. Passive safety cooling pools play a critical role in removing decay heat over long durations during reactor accidents; however, CFD-scale simulations are computationally prohibitive, making it difficult to investigate diverse designs and accident scenarios. CUPID, a 3D two-fluid simulation code, is capable of modeling both single- and two-phase natural circulation phenomena. Its component-scale framework ensures computational efficiency, making it a practical tool for evaluating natural convection and thermal mixing in cooling pools. This study aims to simulate single- to two-phase natural convection in the cooling pool using the CUPID code and validate the approach through comparison with RANS analysis.
Keywords:
Natural circulation
Small modular reactor
CUPID code
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IF:
1.7
Papers:
481
Citations:
1.2W
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