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

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3 Author(s)
Breitkreutz, H. ; Forschungsneutronenquelle Heinz Maier-Leibnitz (FRM II), Garching, Germany ; Röhrmoser, A. ; Petry, W.

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.

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Nuclear Science, IEEE Transactions on  (Volume:57 ,  Issue: 6 )