DocumentCode
1394818
Title
3-Dimensional Coupled Neutronic and Thermal-Hydraulic Calculations for a Compact Core Combining MCNPX and CFX
Author
Breitkreutz, Harald ; Röhrmoser, Anton ; Petry, Winfried
Author_Institution
Forschungsneutronenquelle Heinz Maier-Leibnitz (FRM II), Garching, Germany
Volume
57
Issue
6
fYear
2010
Firstpage
3667
Lastpage
3671
Abstract
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.
Keywords
Monte Carlo methods; computational fluid dynamics; fission reactor cooling; fission reactor core control; fission reactor physics; nuclear engineering computing; 3D coupled neutronic calculations; CFX; FRM II; MCNPX; attached cooling channel; fuel element; neutronic Monte Carlo code; nuclear reactor physics; symmetric compact core; thermal-hydraulic CFD code; thermal-hydraulic calculations; Monte Carlo methods; Nuclear physics; Compact core; coupled neutronic—thermal-hydraulic simulation; research reactor;
fLanguage
English
Journal_Title
Nuclear Science, IEEE Transactions on
Publisher
ieee
ISSN
0018-9499
Type
jour
DOI
10.1109/TNS.2010.2086479
Filename
5658064
Link To Document