Icone11-36118 Thermal Analysis on Mono-Block Type Divertor Based on Subcooled Flow Boiling Critical Heat Flux Data Against Inlet Subcooling in Short Vertical Tube

Hata, Kenji; Tanimoto, Takeya; Komori, Hirokazu; Shiotsu, M.; Noda, N.

doi:10.1299/jsmeicone.2003.240

Cited by 2 publications

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Critical Heat Fluxes of Subcooled Water Flow Boiling Against Outlet Subcooling in Short Vertical Tube

Hata

Shiotsu

Noda

2004

Journal of Heat Transfer

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The critical heat fluxes (CHFs) of subcooled water flow boiling for the test tube inner diameters (d = 3 and 6 mm) and the heated lengths (L = 67, 120 and 150 mm) are systematically measured for the flow velocities (u = 4.0 to 13.3 m/s), the inlet subcoolings (∆T sub,in = 48 to 148 K), the outlet subcoolings (∆T sub,out = 10.5 to 95.1 K), the inlet pressure (P in = 753 to 995 kPa) and the outlet pressure (P out = 720 to 887 kPa). The SUS304 tubes of L = 67, 120 and 150 mm for d = 3 mm and L = 150 mm for d = 6 mm are used. The values of L/d are 22, 40 and 50 for d = 3 mm, and 25 for d = 6 mm, respectively. The CHFs, q cr,sub , for a fixed ∆T sub,out become gradually lower with an increase in the L/d in the whole experimental range. The CHF correlation against outlet subcooling, which has been previously derived for L/d lower than 16, was modified to new one containing the L/d effect based on these experimental data. Furthermore, the relation between q cr,sub and L/d for a fixed ∆T sub,in was checked. The values of q cr,sub for a fixed ∆T sub,in became exponentially lower with the increase in L/d. CHF correlation against inlet subcooling has been given based on the experimental data for L/d ranging from 4.08 to 50. The correlations against outlet and inlet subcoolings can describe not only the CHFs obtained in this work for the inner diameter of 3 and 6 mm at the outlet pressure of around 800 kPa but also the authors' published CHFs data (1 611 points) for the wide ranges of P in = 159 kPa to 1 MPa, d = 3 to 12 mm, L = 33 to 150 mm and u = 4.0 to 13.3 m/s within 15% difference for 30 K ≤ ∆T sub,out ≤ 140 K and 40 K ≤ ∆T sub,in ≤ 151 K.

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Critical Heat Fluxes of Subcooled Water Flow Boiling Against Outlet Subcooling in Short Vertical Tube

Hata

Shiotsu

Noda

2004

Journal of Heat Transfer

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Influence of Test Tube Material on Subcooled Flow Boiling Critical Heat Flux in Short Vertical Tube

Hata

Shiotsu

Noda

2006

Volume 2: Thermal Hydraulics

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The steady state subcooled flow boiling critical heat flux (CHF) for the flow velocities (u = 4.0 to 13.3 m/s), the inlet subcoolings (ΔTsub,in = 48.6 to 154.7 K), the inlet pressure (Pin = 735.2 to 969.0 kPa) and the increasing heat input (Q0exp(t/τ), τ = 10, 20 and 33.3 s) are systematically measured with the experimental water loop. The 304 Stainless Steel (SUS304) test tubes of inner diameters (d = 6 mm), heated lengths (L = 66 mm) and L/d = 11 with the inner surface of rough finished (Surface roughness, Ra = 3.18 μm), the Cupro Nickel (Cu-Ni 30%) test tubes of d = 6 mm, L = 60 mm and L/d = 10 with Ra = 0.18 μm and the Platinum (Pt) test tubes of d = 3 and 6 mm, L = 66.5 and 69.6 mm, and L/d = 22.2 and 11.6 respectively with Ra = 0.45 μm are used in this work. The CHF data for the SUS304, Cu-Ni 30% and Pt test tubes were compared with SUS304 ones for the wide ranges of d and L/d previously obtained and the values calculated by the authors’ published steady state CHF correlations against outlet and inlet subcoolings. The influence of the test tube material on CHF is investigated into details and the dominant mechanism of subcooled flow boiling critical heat flux is discussed.

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Icone11-36118 Thermal Analysis on Mono-Block Type Divertor Based on Subcooled Flow Boiling Critical Heat Flux Data Against Inlet Subcooling in Short Vertical Tube

Cited by 2 publications

References 0 publications

Critical Heat Fluxes of Subcooled Water Flow Boiling Against Outlet Subcooling in Short Vertical Tube

Critical Heat Fluxes of Subcooled Water Flow Boiling Against Outlet Subcooling in Short Vertical Tube

Influence of Test Tube Material on Subcooled Flow Boiling Critical Heat Flux in Short Vertical Tube

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