DRAGON5 and DONJON5, the contribution of Ecole Polytechnique de Montreal to the SALOME platform

被引:32
作者
Hebert, Alain [1 ]
机构
[1] Ecole Polytech, Inst Genie Nucl, Montreal, PQ H3C 3A7, Canada
关键词
Lattice code; Neutron transport; Deterministic solution; Computational scheme; Computer-aided design;
D O I
10.1016/j.anucene.2015.02.033
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 DRAGON lattice code and DONJON full core simulation code are in active development since 1990. A lattice code is used to solve the neutron/photon transport equation using a deterministic approach over a domain corresponding to a subpart or over a complete 2D or 3D nuclear reactor. A full core simulation code includes steady state and transient neutron flux solution capabilities together with reactor operation, micro depletion, and simplified thermal-hydraulics models. The DRAGON and DONJON codes are designed around a scripting language, known as CLE-2000, to automate the flow of information used in computational schemes. DRAGON5 and DONJON5 are the latest version of these codes and features characteristics that are required to design advanced nuclear reactors. First, a new kernel, named GANLIB5, was implemented entirely in ANSI C to facilitate the coupling of the code in multi-physics environments and to permit the embedding in control systems. Second, we added new geometric capabilities to permit the representation of complex geometries that are typical of advanced applications. The first release of DRAGON5 and DONJONS was available in October 2013. Subsequent releases are permitting couplings with the geometry module (Geometry) and supervisor module (YACS) of the SALOME platform. (C) 2015 Elsevier Ltd. All rights reserved.
引用
收藏
页码:12 / 20
页数:9
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