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三维多群 SN 粒子输运代码与蒙特卡罗方法在宫颈癌腔内近距离治疗中的比较。

Comparison of a 3-D multi-group SN particle transport code with Monte Carlo for intracavitary brachytherapy of the cervix uteri.

机构信息

Division of Radiation Oncology, The University of Texas M.D. Anderson Cancer Center, Houston, TX, USA.

出版信息

J Appl Clin Med Phys. 2009 Dec 3;11(1):3103. doi: 10.1120/jacmp.v11i1.3103.

Abstract

A patient dose distribution was calculated by a 3D multi-group S N particle transport code for intracavitary brachytherapy of the cervix uteri and compared to previously published Monte Carlo results. A Cs-137 LDR intracavitary brachytherapy CT data set was chosen from our clinical database. MCNPX version 2.5.c, was used to calculate the dose distribution. A 3D multi-group S N particle transport code, Attila version 6.1.1 was used to simulate the same patient. Each patient applicator was built in SolidWorks, a mechanical design package, and then assembled with a coordinate transformation and rotation for the patient. The SolidWorks exported applicator geometry was imported into Attila for calculation. Dose matrices were overlaid on the patient CT data set. Dose volume histograms and point doses were compared. The MCNPX calculation required 14.8 hours, whereas the Attila calculation required 22.2 minutes on a 1.8 GHz AMD Opteron CPU. Agreement between Attila and MCNPX dose calculations at the ICRU 38 points was within +/- 3%. Calculated doses to the 2 cc and 5 cc volumes of highest dose differed by not more than +/- 1.1% between the two codes. Dose and DVH overlays agreed well qualitatively. Attila can calculate dose accurately and efficiently for this Cs-137 CT-based patient geometry. Our data showed that a three-group cross-section set is adequate for Cs-137 computations. Future work is aimed at implementing an optimized version of Attila for radiotherapy calculations.

摘要

采用 3D 多群 S N 粒子输运代码计算了子宫腔内近距离治疗宫颈癌的患者剂量分布,并与之前发表的蒙特卡罗结果进行了比较。从我们的临床数据库中选择了一个 Cs-137 LDR 腔内近距离治疗 CT 数据集。使用 MCNPX 版本 2.5.c 计算剂量分布。使用 3D 多群 S N 粒子输运代码 Attila 版本 6.1.1 模拟相同的患者。每个患者施源器都在机械设计软件 SolidWorks 中构建,然后进行坐标变换和旋转以适应患者。将 SolidWorks 导出的施源器几何图形导入 Attila 进行计算。在患者 CT 数据集上叠加剂量矩阵。比较剂量体积直方图和点剂量。MCNPX 计算需要 14.8 小时,而在 1.8GHz AMD Opteron CPU 上使用 Attila 计算仅需 22.2 分钟。在 ICRU 38 点处,Attila 和 MCNPX 剂量计算之间的一致性在 +/- 3% 以内。两种代码计算的 2cc 和 5cc 最高剂量体积的剂量差异不超过 +/- 1.1%。剂量和剂量体积直方图的叠加在定性上非常吻合。Attila 可以准确高效地计算这种基于 Cs-137 CT 的患者几何形状的剂量。我们的数据表明,三组截面集足以用于 Cs-137 计算。未来的工作旨在为放射治疗计算实现优化版本的 Attila。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/5065/5719779/2e1adfe4e6be/ACM2-11-002-g001.jpg

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