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

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...

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Veröffentlicht in:IEEE transactions on nuclear science 2010-12, Vol.57 (6), p.3667-3671
Hauptverfasser: Breitkreutz, H, Röhrmoser, A, Petry, W
Format: Artikel
Sprache:eng
Schlagworte:
Channels
Compact core
Computational fluid dynamics
coupled neutronic-thermal-hydraulic simulation
Fuel elements
Marketing
Mathematical analysis
Mathematical models
Monte Carlo methods
Nuclear physics
Nuclear reactors
research reactor
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Beschreibung
Zusammenfassung: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.
ISSN:0018-9499
1558-1578
DOI:10.1109/TNS.2010.2086479