TY - GEN
T1 - Candu three-dimensional neutron-transport calculations with dragon
AU - Shen, Wei
N1 - Publisher Copyright:
© PHYSOR 2002.All right reserved.
PY - 2002
Y1 - 2002
N2 - Within the framework of adopting WIMS-AECL as the Industry Standard Toolset (IST) lattice-cell code for CANDU® analysis, it is imperative that a methodology compatible with this code be implemented for modelling the CANDU fuel bundle, reactivity devices, and fuel channels in three dimensions. The DRAGON code, developed and maintained at École Polytechnique de Montréal, Canada, has been recently selected as an IST code for CANDU three-dimensional (3-D) supercell transport calculations. The DRAGON neutron-transport code was designed for general geometry and can analyze CANDU fuel clusters, light-water reactor assemblies, and fast breeder reactor hexagonal assemblies in two dimensions. The code can also perform 3-D supercell neutron-transport calculations with the same group structures as those used in 2-D analysis. As an IST code, demand for the application of the DRAGON code to CANDU 3-D neutron-transport calculations is increasing. This paper summarizes some applications of DRAGON in CANDU-6 and ACR-700TM reactor-physics and fuel design.
AB - Within the framework of adopting WIMS-AECL as the Industry Standard Toolset (IST) lattice-cell code for CANDU® analysis, it is imperative that a methodology compatible with this code be implemented for modelling the CANDU fuel bundle, reactivity devices, and fuel channels in three dimensions. The DRAGON code, developed and maintained at École Polytechnique de Montréal, Canada, has been recently selected as an IST code for CANDU three-dimensional (3-D) supercell transport calculations. The DRAGON neutron-transport code was designed for general geometry and can analyze CANDU fuel clusters, light-water reactor assemblies, and fast breeder reactor hexagonal assemblies in two dimensions. The code can also perform 3-D supercell neutron-transport calculations with the same group structures as those used in 2-D analysis. As an IST code, demand for the application of the DRAGON code to CANDU 3-D neutron-transport calculations is increasing. This paper summarizes some applications of DRAGON in CANDU-6 and ACR-700TM reactor-physics and fuel design.
UR - https://www.scopus.com/pages/publications/84991086923
M3 - 会议稿件
AN - SCOPUS:84991086923
T3 - Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting
BT - Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology
PB - American Nuclear Society
T2 - 2002 International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing, PHYSOR 2002
Y2 - 7 October 2002 through 10 October 2002
ER -