Title :
3-dimensional coupled neutronic and thermohydraulic calculations for a compact core combining MCNPX and CFX
Author :
Breitkreutz, Harald ; Rohrmoser, Anton ; Petry, Winfried
Author_Institution :
Forschungsneutronenquelle Heinz Maier-Leibnitz (FRM II), Garching, Germany
Abstract :
The neutronic Monte Carlo code MCNPX and the thermohydraulic 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; fission reactor cooling; fission reactor core control; fission reactor design; fission reactor fuel; fission research reactors; 3D coupled neutronic-thermohydraulic calculation; CFX code; FRM II; MCNPX code; compact core; cooling channel; evolute shaped fuel plate; fuel element; neutronic Monte Carlo code; nuclear reactor physics; spatial resolution; Chemical elements; Computational fluid dynamics; Cooling; Fuels; Inductors; Monte Carlo methods; Physics; Shape; Spatial resolution; Temperature; Coupled neutronic; compact core; research reactor; thermohydraulic simulation;
Conference_Titel :
Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2009 First International Conference on
Conference_Location :
Marseille
Print_ISBN :
978-1-4244-5207-1
Electronic_ISBN :
978-1-4244-5208-8
DOI :
10.1109/ANIMMA.2009.5503682
