Critical heat fluxes of subcooled water flow boiling in a short vertical tube at high liquid Reynolds number

• Published in: Nuclear engineering and design 2010-10, Vol.240 (10), p.3145-3157
• Main Authors: Hata, Koichi, Masuzaki, Suguru
• Format: Article
• Language: English
• Subjects: Applied sciences; Boiling; Controled nuclear fusion plants; Correlation; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Flow velocity; Fluid dynamics; Fluid flow; Fuels; Installations for energy generation and conversion: thermal and electrical energy; Liquids; Nuclear fuels; Reynolds number; Water flow
• ISSN: 0029-5493; 1872-759X
• DOI: 10.1016/j.nucengdes.2010.05.035

The steady state critical heat fluxes (CHFs) and the heat transfer of the subcooled water flow boiling for the flow velocities ( u = 17.2–42.4 m/s), the inlet subcoolings (Δ T sub, in = 80.9–147.6 K), the inlet pressures ( P in = 812.1–1181.5 kPa) and the exponentially increasing heat input ( Q 0 exp( t/ τ), τ = 8.5 s) are systematically measured by the experimental water loop comprised of a new multi-stage canned-type circulation pump with high pump head. The SUS304 test tube of inner diameter ( d = 6 mm), heated length ( L = 59.5 mm), L/ d = 9.92 and wall thickness ( δ = 0.5 mm) with surface roughness ( Ra = 3.18 μm) is used in this work. The steady state CHFs of the subcooled water flow boiling for the flow velocities ranging from 17.2 to 42.4 m/s are clarified. The steady state CHFs are compared with the values calculated by our transient CHF correlations against outlet and inlet subcoolings based on the experimental data for the flow velocities ranging from 4.0 to 13.3 m/s. The influence of flow velocity at high liquid Reynolds number on the subcooled flow boiling CHF is investigated in detail and the widely and precisely predictable correlations of the transient CHF correlations against outlet and inlet subcoolings in a short vertical tube are derived based on the experimental data at high liquid Reynolds number. The transient CHF correlations can describe the subcooled flow boiling CHFs for the wide range of flow velocities at high liquid Reynolds number obtained in this work within ±15% difference.