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

fYear

2009

fDate

7-10 June 2009

Firstpage

1

Lastpage

5

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;

fLanguage

English

Publisher

ieee

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

Type

conf

DOI

10.1109/ANIMMA.2009.5503682

Filename

5503682