Development and Implementation of Different Schemes for the Coupling of the System Code ATHLET with the 3D CFD Program ANSYS CFX
(0) In more than thirty years 1D thermal hydraulic system codes have been developed by the nuclear industry and research institutes in order to improve the design and safety of nuclear facilities. Most of these simulation tools are based on the lumped parameter theory, where mass, momentum and energy equations are solved for each fluid phase and balanced over each node of a 1D network. However, since relevant reactor fluid flow and heat transfer phenomena are 3D in nature, 1D system codes have some limitations on their application for specific nuclear reactor safety (NRS) problems with pronounced 3D phenomena like boron dilution, pressurized thermal shock and main steam line break. To overcome these limitations, classical system codes are being coupled with modern computational fluid dynamics (CFD) simulation tools. This paper presents the development and implementation of different schemes for the coupling of the 1D system code ATHLET with the 3D CFD program ANSYS CFX. Comparative analyses with explicit and semi-implicit coupling schemes have been carried out to analyze and improve the performance of the new code ATHLET-ANSYS CFX. Finally, the main advantages and drawbacks of the coupling schemes are discussed.
ANSYS CFX ATHLET coupling schemes advanced simulation tools
Angel Papukchiev Georg Lerchl
Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH Garching-Forschungszentren, Boltzmannstr. 14 85748, Garching n. Munich Germany
国际会议
上海
英文
1612-1623
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）