Burn K W, Daffara C, Gualdrini G, Pierantoni M, Ferrari P
ENEA-Italian National Agency for Energy, New Technologies and the Environment, FIS-NUC, V.M.M. Sole 4, 40129 Bologna, Italy.
Radiat Prot Dosimetry. 2007;123(3):345-53. doi: 10.1093/rpd/ncl150. Epub 2006 Oct 12.
The question of Monte Carlo simulation of radiation transport in voxel geometries is addressed. Patched versions of the MCNP and MCNPX codes are developed aimed at transporting radiation both in the standard geometry mode and in the voxel geometry treatment. The patched code reads an unformatted FORTRAN file derived from DICOM format data and uses special subroutines to handle voxel-to-voxel radiation transport. The various phases of the development of the methodology are discussed together with the new input options. Examples are given of employment of the code in internal and external dosimetry and comparisons with results from other groups are reported.
本文探讨了体素几何结构中辐射输运的蒙特卡罗模拟问题。开发了MCNP和MCNPX代码的补丁版本，旨在以标准几何模式和体素几何处理模式传输辐射。补丁代码读取从DICOM格式数据派生的无格式FORTRAN文件，并使用特殊子程序来处理体素到体素的辐射输运。讨论了该方法开发的各个阶段以及新的输入选项。给出了该代码在体内和体外剂量测定中的应用示例，并报告了与其他团队结果的比较。
