@inproceedings{cf77a9b656ad4fa28453bfad84f1472b,
title = "Implementation and application of the CSG method in the NECP-X code",
abstract = "The CSG (Constructive Solid Geometry) method is widely used in the MC (Monte Carlo) codes because of its flexibility in geometry. In this paper, the CSG method is implemented in NECP-X, which is a newly developed high-fidelity neutronics code, to improve its geometric flexibility. To improve the user experience of using CSG, meshes for the multi-group transport calculation are automatically generated with only several parameters. Several problems are tested. The numerical results show that complicated reactor cores can be conveniently modeled and the results of NECP-X agreed well with those of the MC code.",
keywords = "CSG, Complicated Reactor, MOC, NECP-X",
author = "Lu Cao and Zhouyu Liu and Liangzhi Cao and Qingming He and Xinyu Zhou",
note = "Publisher Copyright: {\textcopyright} 2018-2019 by JSME; 27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019 ; Conference date: 19-05-2019 Through 24-05-2019",
year = "2019",
month = may,
day = "18",
language = "英语",
series = "International Conference on Nuclear Engineering, Proceedings, ICONE",
publisher = "American Society of Mechanical Engineers (ASME)",
booktitle = "Proceedings of the 27th International Conference on Nuclear Engineering, ICONE 2019 - {"}Nuclear Power Saves the World!{"}",
}