Abstract
To estimate fast reactor core transient behavior in three-dimensional geometry, we have applied the improved coarse mesh method to time dependent problems. The improved quasistatic approximation is used with the feedback of fuel temperature change and coolant temperature change. The shape function describing flux distribution is calculated using effective cross sections which are functions of mesh intervals and the amplitude function. To allow large axial coarse meshes with control rod partially inserted, a bilinearly weighting method is used to calculate homogenized cross sections. Using these methods KICOM code has been developed. The validity of this code has been checked by comparing with a two-dimensional transient code FX2-TH for the case when a control rod at core center is withdrawn.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 calculate 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change of a prototype fast reactor and a large fast reactor for the case when a core center rod or an off-center rod is withdrawn. For the prototype reactor, the ...
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