TY - GEN
T1 - The method of characteristics for arbitrary geometry based on the customization of autocad
AU - Chen, Qichang
AU - Wu, Hongchun
AU - Cao, Liangzhi
PY - 2008
Y1 - 2008
N2 - The method of characteristics (MOC) solves the neutron transport equation along each characteristics line. It is independent of the geometry shape of boundary and region. So theoretically, this method can be used to solve neutron transport equation in highly complex geometry. However, we should describe the geometry strictly and calculate intersect points of characteristics line with every boundary and region firstly. complex geometry, due to the great difficulty of treating of arbitrary domain, the selection of geometry shape and efficiency of ray tracing are limited. So in most of the existing codes, the type of outer boundary is limited as rectangular, hexagonal, triangular or the combination of them. in order to treat reflective boundary condition, the selection the azimuthal angles number is not freewill for different outer boundary shapes. To wipe off these limitations for using MOC more complex fuel assembly calculation, the more powerful geometry treatment method is needed. The geometry treatment through the customization of AutoCAD, famous computer aided design software, is given in this paper. Thanks to the powerful capability of AutoCAD in graphics, the description of complex geometry becomes quite convenient. Moreover, with the language VBA (Visual Basic for Applications), AutoCAD can customized to calculate intersect points of each characteristics line with every boundary and region. Thereby, no matter how complex or what kind of the geometry shape is, it be treated uniformly by this method as long as it can be drawn in the AutoCAD. In addition, a directional interpolation method for the treatment of reflective boundary condition is introduced in this paper, so the number of azimuthal angles can be selected freely.
AB - The method of characteristics (MOC) solves the neutron transport equation along each characteristics line. It is independent of the geometry shape of boundary and region. So theoretically, this method can be used to solve neutron transport equation in highly complex geometry. However, we should describe the geometry strictly and calculate intersect points of characteristics line with every boundary and region firstly. complex geometry, due to the great difficulty of treating of arbitrary domain, the selection of geometry shape and efficiency of ray tracing are limited. So in most of the existing codes, the type of outer boundary is limited as rectangular, hexagonal, triangular or the combination of them. in order to treat reflective boundary condition, the selection the azimuthal angles number is not freewill for different outer boundary shapes. To wipe off these limitations for using MOC more complex fuel assembly calculation, the more powerful geometry treatment method is needed. The geometry treatment through the customization of AutoCAD, famous computer aided design software, is given in this paper. Thanks to the powerful capability of AutoCAD in graphics, the description of complex geometry becomes quite convenient. Moreover, with the language VBA (Visual Basic for Applications), AutoCAD can customized to calculate intersect points of each characteristics line with every boundary and region. Thereby, no matter how complex or what kind of the geometry shape is, it be treated uniformly by this method as long as it can be drawn in the AutoCAD. In addition, a directional interpolation method for the treatment of reflective boundary condition is introduced in this paper, so the number of azimuthal angles can be selected freely.
UR - https://www.scopus.com/pages/publications/70249086279
U2 - 10.1115/ICONE16-48605
DO - 10.1115/ICONE16-48605
M3 - 会议稿件
AN - SCOPUS:70249086279
SN - 0791848159
SN - 9780791848159
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
SP - 877
EP - 882
BT - 2008 Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16
T2 - 16th International Conference on Nuclear Engineering, ICONE16 2008
Y2 - 11 May 2008 through 15 May 2008
ER -