This paper presents a thermal-hydraulic model of the straight-tube Once-Through Steam Generator (OTSG) of the Sodium-cooled Fast Reactor (SFR) and its application to analyze the hydrodynamic characteristic in an OTSG. The calculated region is divided into four regions, namely subcooled region, nucleate boiling region, film boiling region, and superheated region. Drift-flux model is adopted for two-phase region. The governing equations are based on the mass, energy and momentum equations. The hydrodynamic characteristic is obtained from numerical iterations of the steady-state governing equations. A code named SGCODE is developed by this model and is verified with nominal design data of this OTSG. The influence factors including inlet water throttling coefficient, inlet sodium volume flow rate, and inlet sodium temperature are analyzed.
Analysis of Hydrodynamic Characteristic in Straight-Tube Sodium-Heated Once-Through Steam Generator
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Zhong, X, Yu, J, Saeed, M, Yang, C, & Zhang, X. "Analysis of Hydrodynamic Characteristic in Straight-Tube Sodium-Heated Once-Through Steam Generator." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 6: Thermal-Hydraulics. Shanghai, China. July 2–6, 2017. V006T08A014. ASME. https://doi.org/10.1115/ICONE25-66226
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