TY - JOUR
T1 - Predictions of rewetting process for a nuclear fuel rod using first-principles equations
AU - Ferng, Y. M.
AU - Chieng, C. C.
AU - Pan, C.
PY - 1991/4/2
Y1 - 1991/4/2
N2 - The rewetting of a nuclear fuel rod is investigated numerically by a conjugated heat transfer model using first-principles equations. The two-phase flow in the coolant channel is treated by a turbulent, locally-homogenized model. The heat transfer coefficient, rewetting temperature and rewetting velocity are parts of the solution. The critical heat flux predicted by the model agrees with the experimental data available in other literature to a reasonable extent. The effect of gap resistance on the rewetting process is studied and the results show agreement with earlier analytical models. The predicted rewetting velocity agrees with experimental data within 15% discrepancy. © 1991.
AB - The rewetting of a nuclear fuel rod is investigated numerically by a conjugated heat transfer model using first-principles equations. The two-phase flow in the coolant channel is treated by a turbulent, locally-homogenized model. The heat transfer coefficient, rewetting temperature and rewetting velocity are parts of the solution. The critical heat flux predicted by the model agrees with the experimental data available in other literature to a reasonable extent. The effect of gap resistance on the rewetting process is studied and the results show agreement with earlier analytical models. The predicted rewetting velocity agrees with experimental data within 15% discrepancy. © 1991.
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U2 - 10.1016/0029-5493(91)90110-4
DO - 10.1016/0029-5493(91)90110-4
M3 - RGC 21 - Publication in refereed journal
SN - 0029-5493
VL - 126
SP - 189
EP - 205
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
IS - 2
ER -