Development of multi-physics code systems based on the reactor dynamics code DYN3D

被引：20

作者：

Kliem, S. ^{[1
]}

Gommlich, A. ^{[1
]}

Grahn, A. ^{[1
]}

Rohde, U. ^{[1
]}

Schuetze, J. ^{[2
]}

Frank, T. ^{[3
]}

Gomez, A. ^{[4
]}

Sanchez, V. ^{[4
]}

机构：

[1] Helmholtz Zentrum Dresden Rossendorf, D-01328 Dresden, Germany

[2] ANSYS Germany GmbH, D-64295 Darmstadt, Germany

[3] ANSYS Germany GmbH, D-83624 Otterfing, Germany

[4] Karlsruhe Inst Technol, D-76344 Eggenstein Leopoldshafen, Germany

来源：

KERNTECHNIK | 2011年 / 76卷 / 03期

关键词：

BENCHMARK; DYN3D/ATHLET; VALIDATION; WATER;

D O I：

10.3139/124.110146

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The reactor dynamics code DYN3D has been coupled with the CFD code ANSYS CFX and the 3D thermal hydraulic core model FLICA4. In the coupling with ANSYS CFX, DYN3D calculates the neutron kinetics and the fuel behavior including the heat transfer to the coolant. The physical data interface between the codes is the volumetric heat release rate into the coolant. In the coupling with FLICA4 only the neutron kinetics module of DYN3D is used. Fluid dynamics and related transport phenomena in the reactor's coolant and fuel behavior is calculated by FLICA4. The correctness of the coupling of DYN3D with both thermal hydraulic codes was verified by the calculation of different test problems. These test problems were set-up in such a way that comparison with the DYN3D stand-alone code was possible. This included steady-state and transient calculations of a mini-core consisting of nine real-size PWR fuel assemblies with ANSYS CFX/DYN3D as well as mini-core and a full core steady-state calculation using FLICA4/DYN3D.

引用

页码：160 / 165

页数：6

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