  |
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.
From S. Kliem | A. Gommlich | A. Grahn | U. Rohde | J. Schütze | T. Frank | A. Gomez | V. Sanchez
(Received 14.02.2011)
Appeared in Kerntechnik 2011/03, Page 160-165
Direct link: http://www.nuclear-engineering-journal.com/KT110146
Pay content
Development of multi-physics code systems based on the reactor dynamics code DYN3D [485 KB]
This service is free for subscribers of Kerntechnik.
References
1 Grundmann, U.; Rohde, U.; Mittag, S.: DYN3D – Three Dimensional Core Model for Steady-State and Transient Analysis of Thermal Reactors. Proc. PHYSOR2000, Pittsburgh, CD-ROM.
2 Beckert, C.; Grundmann, U.:Development and verification of a nodal approach for solving the multigroup SP3 equations. Annals of Nuclear Energy 35/1 (2008) 75.
3 Duerigen, S.; Grundmann, U.; Mittag, S.: A nodal approach to the solution of the multi-group SP3 equations in trigonal geometry. Proc. Annual Meeting on Nuclear Technology ’10, paper 107, INFORUM GmbH, Berlin (2010).
4 ANSYS Inc., ANSYS 12.0 User’s Guide, Canonsburg, PA, USA (2009).
5 Chauliac, C.: Overview on the Collaborative Project NURISP. Presentation at the NURESIM General Seminar, Madrid, Nov. 27–28, 2008.
6 http://www.salome-platform.org/.
7 Toumi, I.; Bergeron, A.; Gallo, D.; Royer, E.; Caruge, D.: FLICA-4: A 3D two-phase flow computer code with advanced numerical methods for nuclear applications. Nucl. Eng. Design 200 (2000) 139 – 155.
8 Kozmenkov, Y.; Kliem, S.; Grundmann, U.; Rohde, U.; Weiss, F.-P.: Calculation of the VVER-1000 coolant transient benchmark using the coupled code systems DYN3D/RELAP5 and DYN3D/ATHLET. Nucl. Eng. Design 237 (2007) 1938 – 1951.
9 Kliem, S.; Kozmenkov, Y.; Hoehne, T.; Rohde U.: Analyses of the V1000CT-1 benchmark with the DYN3D/ATHLET and DYN3D/RELAP coupled code systems including a coolant mixing model validated against CFD calculations. Progress in Nucl. Energy 48 (2006) 830–848.
10 Mittag S.; Kliem, S.; Weis, F.-P.; Kyrki-Rajamäki, R.; Hämäläinen, A.; Langenbuch, S.; Danilin, S.; Hadek, J.; Hegyi, G.; Kuchin, A.; Panayotov, D.: Validation of coupled neutron kinetic / thermal-hydraulic codes Part 1: Analysis of a VVER-1000 transient (Balakovo-4), Annals of Nuclear Energy, 28/9 (2001), pp. 857 –873.
11 Grundmann, U.; Kliem, S.: Analyses of the OECD main steam line break benchmark with the DYN3D and ATHLET codes. Nuc. Techn. 142 (2003) 146–153.
12 Kliem, S.; Rohde, U.; Weiss, F.-P.: Core response of a PWR to a slug of under-borated water. Nucl. Eng. Design 230 (2004) 121–132.
13 Rohde, U.; Hoehne, T.; Kliem, S.; Hemström, B.; Scheuerer, M.; Toppila, T.; Aszodi, A.; Boros, I.; Farkas, I.; Muhlbaur, P.; Vyskocil, V.; Klepac, J.; Remis, J.; Dury, T.: Fluid mixing and flow distribution in the reactor circuit – Computational fluid dynamics code validation. Nucl. Eng. Design 237 (2007) 1639–1655.
14 Zerkak, O.; et al.: LWRMultiphysics developments and applications within the framework of the NURESIM European project. Proc. M & C + SNA 2007, CD-ROM, 15. –19.04.2007, Monterey, USA.
15 Frank, Th.; Lifante, C.;Waata, C.L.; Schuetze, J.: Final Report in the German GRS-BMWi Project No. 150–1328 “Development of CFD Software for Simulation of Multidimensional Flows in Reactor Cooling Systems”. ANSYS Germany GmbH, Otterfing, Germany, ANSYS Technical Report ANSYS/TR-09-02, (2010).
|
| © 2013 by Carl Hanser Verlag |
Navigation
- Current issue
- Volumes
- Search
- Sponsored articles
- Top 20 Downloads
Subscriber Support
abo-service@hanser.de
For authors:
Information on article submission
- Volumes
- Search
- Sponsored articles
- Top 20 Downloads
Subscriber Support
abo-service@hanser.de
For authors:
Information on article submission
Document number