Multi-scale coupling of CFD code and sub-channel code based on a generic coupling architecture

被引:13
作者
Zhang, Xilin [1 ]
Zhang, Kanglong [2 ]
Sanchez-Espinoza, V. H. [2 ]
Chen, Hongli [1 ]
机构
[1] Univ Sci & Technol China, Sch Phys Sci, Hefei 230027, Anhui, Peoples R China
[2] Karlsruhe Inst Technol, Inst Neutron Phys & Reactor, D-76344 Eggenstein Leopoldshafen, Germany
关键词
Coupling; Sub-channel code; CFD code; ICoCo; MEDCoupling; VALIDATION;
D O I
10.1016/j.anucene.2020.107353
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
This paper describes a multi-scale thermal-hydraulic coupling system, which combines the capabilities of the open-source TrioCFD code and of the sub-channel code SubChanFlow (SCF) aiming to improve the description and prediction of the multi-scale thermal-hydraulic physical phenomenon inside the reactor vessel. This is a parallel coupling system based on the ICoCo (Interface for Code Coupling) concept, where each code is first wrapped by the ICoCo interface and then it is compiled to a shared library. A parallel C++ script was developed as the supervisor, which utilizes the two shared libraries and supervises the calculation of the coupled system. The MEDCoupling libraries developed by CEA provide a generic way to handle the mesh interpolation and field mapping between different domains of TrioCFD and SCF. Moreover, the explicit temporal coupling method and the domain-decomposition approach are adopted and presented in this paper. An academic problem is developed to test the multi-scale coupling code. The results indicate that the inter-code data exchange works well and that the coupled code TrioCFD/SCF can deal with various time-dependent boundary conditions.(C) 2020 Elsevier Ltd. All rights reserved.
引用
收藏
页数:11
相关论文
共 33 条
  • [1] Angeli PE., 2015, Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH16), P252
  • [2] [Anonymous], 1999, COBRA EN UPGRADED VE
  • [3] [Anonymous], OPENFOAM US GUID
  • [4] ANSYS CFX, 2009, ANSYS CFX 12 0 US GU
  • [5] ANSYS FLUENT, 2009, ANSYS FLUENT 12 0 US
  • [6] A Survey of Open Source Multiphysics Frameworks in Engineering
    Babur, Onder
    Smilauer, Vit
    Verhoeff, Tom
    van den Brand, Mark
    [J]. INTERNATIONAL CONFERENCE ON COMPUTATIONAL SCIENCE, ICCS 2015 COMPUTATIONAL SCIENCE AT THE GATES OF NATURE, 2015, 51 : 1088 - 1097
  • [7] A first system/CFD coupled simulation of a complete nuclear reactor transient using CATHARE2 and TRIO_U. Preliminary validation on the Phenix Reactor Natural Circulation Test
    Baviere, R.
    Tauveron, N.
    Perdu, F.
    Garre, E.
    Li, S.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2014, 277 : 124 - 137
  • [8] Automated scientific software scripting with SWIG
    Beazley, DM
    [J]. FUTURE GENERATION COMPUTER SYSTEMS, 2003, 19 (05) : 599 - 609
  • [9] Bertolotto D., 2011, COUPLING SYSTEM CODE
  • [10] CFD analysis and experimental validation of steady state mixed convection sodium flow
    Bieder, U.
    Ziskind, G.
    Rashkovan, A.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2018, 326 : 333 - 343