Institute for Integrated Radiation and Nuclear Science, Kyoto University, Sennangun, Osaka, Japan.
Kansai BNCT Medical Center, Osaka Medical and Pharmaceutical University, Takatsuki, Osaka, Japan.
Med Phys. 2024 Jun;51(6):4413-4422. doi: 10.1002/mp.17093. Epub 2024 Apr 26.
Monte Carlo simulation code is commonly used for the dose calculation of boron neutron capture therapy. In the past, dose calculation was performed assuming a homogeneous mass density and elemental composition inside the tissue, regardless of the patient's age or sex. Studies have shown that the mass density varies with patient to patient, particularly for those that have undergone surgery or radiotherapy. A method to convert computed tomography numbers into mass density and elemental weights of tissues has been developed and applied in the dose calculation process using Monte Carlo codes. A recent study has shown the variation in the computed tomography number between different scanners for low- and high-density materials.
The aim of this study is to investigate the effect of the elemental composition inside each calculation voxel on the dose calculation and the application of the stoichiometric CT number calibration method for boron neutron capture therapy planning.
Monte Carlo simulation package Particle and Heavy Ion Transport code System was used for the dose calculation. Firstly, a homogeneous cubic phantom with the material set to ICRU soft tissue (four component), muscle, fat, and brain was modelled and the NeuCure BNCT system accelerator-based neutron source was used. The central axis depth dose distribution was simulated and compared between the four materials. Secondly, a treatment plan of the brain and the head and neck region was simulated using a dummy patient dataset. Three models were generated; (1) a model where only the fundamental materials were considered (simple model), a model where each voxel was assigned a mass density and elemental weight using (2) the Nakao20 model, and (3) the Schneider00 model. The irradiation conditions were kept the same between the different models (irradiation time and irradiation field size) and the near maximum (D) and mean dose to the organs at risk were calculated and compared.
A maximum percentage difference of approximately 5% was observed between the different materials for the homogeneous phantom. With the dummy patient plan, a large dose difference in the bone (greater than 12%) and region near the low-density material (mucosal membrane, 7%-11%) was found between the different models.
A stoichiometric CT number calibration method using the newly developed Nakao20 model was applied to BNCT dose calculation. The results indicate the importance of calibrating the CT number to elemental composition for each individual CT scanner for the purpose of BNCT dose calculation along with the consideration of heterogeneity of the material composition inside the defined region of interest.
蒙特卡罗模拟代码常用于硼中子俘获治疗的剂量计算。过去,剂量计算是在假设组织内的质量密度和元素组成均匀的情况下进行的,而不考虑患者的年龄或性别。研究表明,质量密度因人而异,特别是那些接受过手术或放疗的患者。已经开发出一种将计算机断层扫描(CT)数转换为组织质量密度和元素重量的方法,并已将其应用于使用蒙特卡罗代码进行的剂量计算中。最近的一项研究表明,不同扫描仪对低密度和高密度材料的 CT 数存在差异。
本研究旨在探讨每个计算体素内的元素组成对剂量计算的影响,并应用化学计量 CT 数校准方法进行硼中子俘获治疗计划。
使用蒙特卡罗模拟软件包Particle and Heavy Ion Transport code System 进行剂量计算。首先,对一个具有 ICRU 软组织(四成分)、肌肉、脂肪和大脑材料的均匀立方体模型进行建模,并使用 NeuCure BNCT 系统加速器基中子源进行模拟。模拟了中心轴深度剂量分布,并比较了四种材料的分布。其次,使用虚拟患者数据集模拟脑和头颈部的治疗计划。生成了三个模型;(1)仅考虑基本材料的模型(简单模型),(2)使用 Nakao20 模型为每个体素分配质量密度和元素重量的模型,以及(3)Schneider00 模型。不同模型之间保持相同的照射条件(照射时间和照射野大小),计算并比较了危险器官的近最大(D)和平均剂量。
对于均匀体模,不同材料之间的最大差异约为 5%。对于虚拟患者计划,在不同模型之间,骨(大于 12%)和低密度材料附近的区域(黏膜,7%-11%)的剂量差异较大。
使用新开发的 Nakao20 模型的化学计量 CT 数校准方法已应用于 BNCT 剂量计算。结果表明,为了进行 BNCT 剂量计算,必须根据每个特定的 CT 扫描仪校准 CT 数与元素组成,并考虑感兴趣区域内材料组成的异质性。