3-Dimensional Coupled Neutronic and Thermal-Hydraulic Calculations for a Compact Core Combining MCNPX and CFX

The neutronic Monte Carlo code MCNPX and the thermal-hydraulic CFD code CFX have been coupled to satisfy the increasing demand for 3-dimensional results with high spatial resolution in nuclear reactor physics. In a first step, results for an evolute shaped fuel plate of a symmetric compact core and an attached cooling channel in the fuel element of FRM II were regarded.