@inproceedings{8e85feaba6a94567813ab64750ab9efa,
title = "Determinant methods for solving neutron transport equation in unstructured geometry",
abstract = "The spherical harmonics (Pn) finite element method, the Sn finite element method, the triangle transmission probability method and the discrete triangle nodal method were all introduced to solve the neutron transport equation for unstructured fuel assembly respectively. The computing codes of each method were encoded and numerical results were discussed and compared. It was demonstrated that these four methods can solve neutron transport equations with unstructured-meshes very effectively and correctly, they can be used to solve unstructured fuel assembly problem.",
keywords = "Fuel assembly, Neutron transport, Numerical calculation, Unstructured",
author = "Hongchun Wu and Guoming Liu and Liangzhi Cao and Qichang Chen",
year = "2010",
doi = "10.1115/ICONE18-29442",
language = "英语",
isbn = "9780791849309",
series = "International Conference on Nuclear Engineering, Proceedings, ICONE",
booktitle = "18th International Conference on Nuclear Engineering, ICONE18",
note = "18th International Conference on Nuclear Engineering, ICONE18 ; Conference date: 17-05-2010 Through 21-05-2010",
}