<p>Forced convection subcooled
boiling flow is an efficient heat transfer process due to the latent heat of
evaporation as well as the agitated convection induced by the departure of bubbles.
In order to predict and hence prevent the possible occurrence of critical heat
flux (CFH) at the heated wall, efforts are made to improve the predictability
of wall nucleation boiling models. In this study, simulations are performed using
3-D CFD code ANSYS CFX to assess the predictive capabilities of 42 combinations
of nucleation boiling models versus four experimental conditions. Simulation
results show that no specific model combination can consistently give the best
performance. Also, two major discrepancies are found in the local void fraction
profile prediction as well as the wall temperature profile prediction:</p>
<p>1.
Most of the local
void fraction profile prediction results show smaller void fractions than the
experimental data near the heated wall as well as in the bulk region.</p>
<p><a>2.
All of the wall temperature profile prediction
results show monotonically increasing trend, which is different from the
decreasing-increasing pattern of the experimental data.</a></p>
<p>The first discrepancy is improved
by using the Chen correlation in place of the bubble departure frequency model.
The second discrepancy is improved by using modified
single-phase heat transfer coefficient, which accounts for the pumping effect
and the vapor blanket effect. The influence of condensation is also discussed by using variable bulk bubble diameter in place of the Laplace length. This simulation work is the first one in the
literature that captures the decreasing-increasing pattern of the wall
temperature profile. Although the local void fraction profile prediction and the
wall temperature profile prediction are improved, the predicted departure
frequency is much higher than the experimental data. In order to understand the
possible reason for this discrepancy, more data for the important parameters, e.g., departure frequency, departure diameter, active nucleation site density, etc., along the whole flow channel
are needed as the future work.</p>