TY - JOUR
T1 - Cooling capacity of plate type research reactors during the natural convective cooling mode
AU - Jo, Daeseong
AU - Park, Suki
AU - Park, Jonghark
AU - Chae, Heetaek
AU - Lee, Byungchul
PY - 2012/4
Y1 - 2012/4
N2 - Numerical investigations on the cooling capacity of plate type research reactors during the natural convective cooling mode are fulfilled in the present study. The cooling capacity, as a thermal core design criterion, is determined by the onset of nucleate boiling (ONB) temperature margin. A simplified model, consisting of the lower plenum, the core, the chimney, the flap valve, and the pool, is simulated by RELAP5/MOD3 and NATCON. The axial and radial peaking factors for the power distribution are applied to investigate the cooling capacity on the hot spot in a fuel assembly. Several convective heat transfer correlations developed by Dittus and Boelter (1930), Petukhov (1970), and Sudo et al. (1985) are implemented into the simulations; then the coolant and surface temperatures and ONB temperature margin, as a function of core power, are obtained from the simulations. The comparisons between RELAP5/MOD3 and NATCON simulations are in good agreement, and the lowest cooling capacity, which limits the permissible core power during the natural convection cooling, is found with Sudo heat transfer correlation.
AB - Numerical investigations on the cooling capacity of plate type research reactors during the natural convective cooling mode are fulfilled in the present study. The cooling capacity, as a thermal core design criterion, is determined by the onset of nucleate boiling (ONB) temperature margin. A simplified model, consisting of the lower plenum, the core, the chimney, the flap valve, and the pool, is simulated by RELAP5/MOD3 and NATCON. The axial and radial peaking factors for the power distribution are applied to investigate the cooling capacity on the hot spot in a fuel assembly. Several convective heat transfer correlations developed by Dittus and Boelter (1930), Petukhov (1970), and Sudo et al. (1985) are implemented into the simulations; then the coolant and surface temperatures and ONB temperature margin, as a function of core power, are obtained from the simulations. The comparisons between RELAP5/MOD3 and NATCON simulations are in good agreement, and the lowest cooling capacity, which limits the permissible core power during the natural convection cooling, is found with Sudo heat transfer correlation.
KW - Natural convective cooling
KW - Onset of nucleate boiling margin
KW - Plate type research reactor
KW - Rectangular channel
UR - http://www.scopus.com/inward/record.url?scp=84862829638&partnerID=8YFLogxK
U2 - 10.1016/j.pnucene.2011.12.018
DO - 10.1016/j.pnucene.2011.12.018
M3 - Article
AN - SCOPUS:84862829638
SN - 0149-1970
VL - 56
SP - 37
EP - 42
JO - Progress in Nuclear Energy
JF - Progress in Nuclear Energy
ER -