Institute for Nuclear Waste Disposal Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany.
Health Phys. 2012 Feb;102(2):221-9. doi: 10.1097/HP.0b013e3182321cdb.
Voxel2MCNP is a program that sets up radiation protection scenarios with voxel models and generates corresponding input files for the Monte Carlo code MCNPX. Its technology is based on object-oriented programming, and the development is platform-independent. It has a user-friendly graphical interface including a two- and three-dimensional viewer. A row of equipment models is implemented in the program. Various voxel model file formats are supported. Applications include calculation of counting efficiency of in vivo measurement scenarios and calculation of dose coefficients for internal and external radiation scenarios. Moreover, anthropometric parameters of voxel models, for instance chest wall thickness, can be determined. Voxel2MCNP offers several methods for voxel model manipulations including image registration techniques. The authors demonstrate the validity of the program results and provide references for previous successful implementations. The authors illustrate the reliability of calculated dose conversion factors and specific absorbed fractions. Voxel2MCNP is used on a regular basis to generate virtual radiation protection scenarios at Karlsruhe Institute of Technology while further improvements and developments are ongoing.
体素到 MCNP 转换器是一个用体素模型建立辐射防护场景并为蒙特卡罗代码 MCNPX 生成相应输入文件的程序。它的技术基于面向对象编程，开发与平台无关。它具有用户友好的图形界面，包括二维和三维查看器。程序中实现了一排设备模型。支持各种体素模型文件格式。应用包括计算体内测量场景的计数效率和计算内外辐射场景的剂量系数。此外，还可以确定体素模型的人体测量参数，例如胸壁厚度。体素到 MCNP 转换器提供了几种体素模型操作方法，包括图像配准技术。作者证明了程序结果的有效性，并为以前的成功实现提供了参考。作者说明了计算剂量转换因子和比吸收率的可靠性。体素到 MCNP 转换器在卡尔斯鲁厄理工学院定期用于生成虚拟辐射防护场景，同时还在进行进一步的改进和开发。
