水准点(测量)
计算
中子输运
中子通量
瞬态(计算机编程)
中子
计算机科学
维数(图论)
编码(集合论)
应用数学
物理
计算物理学
统计物理学
数学
算法
核物理学
大地测量学
集合(抽象数据类型)
纯数学
程序设计语言
地理
操作系统
作者
Y. Fontenla,A. Vidal-Ferràndiz,A. Carreño,D. Ginestar,G. Verdú
标识
DOI:10.1016/j.anucene.2023.110239
摘要
FEMFFUSION is an open source code that solves the multigroup neutron transport equation using the diffusion and the SPN approximations. This code uses the continuous Galerkin finite element method to be able to deal with any type of geometry, structured or unstructured, and problem dimension. To verify the program, a research study of the two-dimensional C5G7 benchmark has been performed, including the static, time-dependent and neutron noise computations. Numerical results include the effective multiplication factor, keff, the spatial neutron fluxes, and neutron power distributions for the static computations. The total neutron power evolution of a given transient and the neutron flux distribution evolution for the different energy groups. In addition, neutron noise frequency domain calculation were completed for perturbations of some cross-section in the reactor core. All computation have been performed using different SPN approximations. FEMFFUSION results are verified against the official OECD/NEA benchmark results.
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