SUS304 Tubes Research Articles

ICONE11-36116 CRITICAL HEAT FLUXES OF SUBCOOLED WATER FLOW BOILING AGAINST INLET SUBCOOLING IN SHORT VERTICAL TUBE

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&le;ΔT_<sub, out>&le;140K and 40 K&le;ΔT_<sub, in>&le;151 K.

Tritium release behavior from molten lithium-lead alloy by permeation through stainless steel type 304

Tritium release behavior through stainless steel type 304 as a structural material in the presence of molten lithium-lead alloy (Li 17 Pb 83 ) was studied at 600°C under neutron irradiation, The tritium permeation ratio to the secondary purge gas line was affected by the existence of H 2 in the purge gas. The tritium permeation rate changed with elapsed time, and decreased by 70% after 20 days since the start of an experimental series. This is attributed to the formation of an oxide layer on the SUS304 surface that is stable in H 2 atmosphere. An analytical model was applied to the experimental data on tritium release to obtain the mass transfer coefficient of tritium through the SUS304 tube.