T. Takeda et al., 3-DIMENSIONAL TRANSIENT ANALYSIS OF FAST-REACTORS WITH IMPROVED COARSE MESH METHOD, Journal of Nuclear Science and Technology, 31(1), 1994, pp. 12-23
To estimate fast reactor core transient behavior in three-dimensional
geometry, we have applied the improved coarse mesh method to time depe
ndent problems. The improved quasistatic approximation is used with th
e feedback of fuel temperature change and coolant temperature change.
The shape function describing flux distribution is calculated using ef
fective cross sections which are functions of mesh intervals and the a
mplitude function. To allow large axial coarse meshes with control rod
partially inserted, a bilinearly weighting method is used to calculat
e homogenized cross sections. Using these methods KICOM code has been
developed. The validity of this code has been checked by comparing wit
h a two-dimensional transient code FX2 TH for the case when a control
rod at core center is withdrawn. The KICOM code has been applied to ca
lculate the power change of a prototype fast reactor and a large fast
reactor for the case when a core center rod or an off-center rod is wi
thdrawn. For the prototype reactor. the reactor power rapidly changes
with time. but the power distribution (shape function) remains almost
the same. However. for the large fast reactor, not only the reactor po
wer but also the power distribution remarkably change with time. The m
esh effect is also investigated by comparing the results with and with
out the mesh correction.