Franck D, Borissov N, de Carlan L, Pierrat N, Genicot J L, Etherington G
Institut de Radioprotection et de Sûreté Nucléaire, Département de Protection de la Santé de l'Homme et de Dosimétrie, IRSN, BP no 17, F-92262 Fontenay-aux-Roses Cedex, France.
Radiat Prot Dosimetry. 2003;105(1-4):403-8. doi: 10.1093/oxfordjournals.rpd.a006269.
This paper reports on a new utility for development of computational phantoms for Monte Carlo calculations and data analysis for in vivo measurements of radionuclides deposited in tissues. The individual parameters of each worker can be acquired for an exact geometric representation of his or her anatomy, which is particularly important for low-energy gamma ray emitting sources such as thorium, uranium, plutonium and other actinides. The software discussed here enables automatic creation of an MCNP input data file based on computed tomography (CT) scanning data. The utility was first tested for low- and medium-energy actinide emitters on Livermore phantoms, the mannequins generally used for lung counting, in order to compare the results of simulation and measurement. From these results, the utility's ability to study uncertainties in in vivo calibration were investigated. Calculations and comparison with the experimental data are presented and discussed in this paper.
本文报道了一种新的实用工具，用于开发计算体模，以进行蒙特卡罗计算和数据分析，用于体内测量沉积在组织中的放射性核素。可以获取每个工作人员的个体参数，以便精确地几何表示其解剖结构，这对于诸如钍、铀、钚和其他锕系元素等低能伽马射线发射源尤为重要。这里讨论的软件能够基于计算机断层扫描（CT）扫描数据自动创建MCNP输入数据文件。该实用工具首先在利弗莫尔体模（通常用于肺部计数的人体模型）上针对低能和中能锕系元素发射体进行了测试，以便比较模拟和测量结果。根据这些结果，研究了该实用工具研究体内校准不确定性的能力。本文展示并讨论了计算结果以及与实验数据的比较。
