Abstract
The critical heat fluxes (CHFs) of subcooled water flow boiling for the test tube inner diameters (d-3 and 6mm) and the heated lengths (L=67,120 and 150mm) are systematically measured for the flow velocities (u=4.0 to 13.3m/c), the inlet subcoolings (ΔT_<sub, in>=48 to 148 K), the outlet subcoolings (ΔT_<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 150mm for d=3mm and L=150mm for d=6mm are used. The values of L/d are 22,40 and 50 for d=3mm, and 25 for d=6mm, respectively. The CHFs, q_<cr, sub>, for a fixed ΔT_<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 ΔT_<sub, in> was checked. The values of q_<cr, sub> for a fixed ΔT_<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 6mm at the outlet pressure of around 800 kPa but also the authors' published CHFs data (1611 points) for the wide ranges of P_<in>=159 kPa to 1 MPa, d=3 to 12mm, L=33 to 150mm and u=4.0 to 13.3 m/s within 15% difference for 30 K≤ΔT_<sub, out>≤140K and 40 K≤ΔT_<sub, in>≤151 K.
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More From: The Proceedings of the International Conference on Nuclear Engineering (ICONE)
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