Page 214 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

Subchannel analysis for LMR 5

X. Cheng
KIT, Karlsruhe, Germany

Nomenclature

2
A area (m )
C P specific heat (J/kgK)
D rod diameter (m)
D h hydraulic diameter (m)
D w wire diameter (m)
E energy flow rate (J/s)
f friction coefficient
f m , f M , f H correction factor for mixing coefficients
2
G mass flux (kg/m s)
h specific enthalpy (J/kg)
H wire pitch (m)
HTC N normalized heat-transfer coefficient
k pressure-drop coefficient of DC flow
k s pressure-loss coefficient of spacer
l length scale (m)
l t turbulent mixing length (m)
m mass flow rate (kg/s)
Nu Nusselt number
P pitch (m)
p pressure (Pa)
Pe Peclet number
Pr Prandtl number
2
q heat flux (W/m )
Q power (W)
Re Reynolds number
s gap width (m)
T temperature (°C)
u velocity (m/s)
u e effective velocity (m/s)
3
V volume (m )
coordinates (m)
x, y,z

Greek symbols

α heat-transfer coefficient (W/m K)
2
β mixing coefficient
μ dynamic viscosity (Pas)

Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors. https://doi.org/10.1016/B978-0-08-101980-1.00005-3
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