Gadan M, Crawley V, Thorp S, Miller M
Favaloro University, Argentina.
Appl Radiat Isot. 2009 Jul;67(7-8 Suppl):S206-9. doi: 10.1016/j.apradiso.2009.03.051. Epub 2009 Mar 27.
As a part of the project concerning the irradiation of a section of the human liver left lobe, a preliminary estimation of the expected dose was performed. To obtain proper input values for the calculation, neutron flux and gamma dose rate characterization were carried out using adequate portions of cow or pig liver covered with demineralized water simulating the preservation solution. Irradiations were done inside a container specially designed to fulfill temperature preservation of the organ and a reproducible irradiation position (which will be of importance for future planification purposes). Implantable rhodium based self-powered neutron detectors were developed to obtain neutron flux profiles both external and internal. Implantation of SPND was done along the central longitudinal axis of the samples, where lowest flux is expected. Gamma dose rate was obtained using a neutron shielded graphite ionization chamber moved along external surfaces of the samples. The internal neutron profile resulted uniform enough to allow for a single and static irradiation of the liver. For dose estimation, irradiation condition was set in order to obtain a maximum of 15 Gy-eq in healthy tissue. Additionally, literature reported boron concentrations of 47 ppm in tumor and 8 ppm in healthy tissue and a more conservative relationship (30/10 ppm) were used. To make a conservative estimation of the dose the following considerations were done: i). Minimum measured neutron flux inside the sample (approximately 5 x 10(9) n cm-2 s-1) was considered to calculate dose in tumor. (ii). Maximum measured neutron flux (considering both internal as external profiles) was used to calculate dose in healthy tissue (approximately 8.7 x 10(9) n cm-2 s-1). (iii). Maximum measured gamma dose rate (approximately 13.5 Gy h-1) was considered for both tumor and healthy tissue. Tumor tissue dose was approximately 69 Gy-eq for 47 ppm of (10)B and approximately 42 Gy-eq for 30 ppm, for a maximum dose of 15 Gy-eq in healthy tissue. As can be seen from these results, even for the most conservative case, minimum tumor dose will be acceptable from the treatment point of view, which shows that the irradiation conditions at this facility have quite good characteristics for the proposed irradiation.
作为人体肝脏左叶部分照射项目的一部分,对预期剂量进行了初步估算。为了获得计算所需的合适输入值,使用覆盖有模拟保存溶液的去离子水的适量牛肝或猪肝部分进行了中子通量和伽马剂量率表征。辐照在专门设计的容器内进行,该容器可实现器官的温度保持和可重复的辐照位置(这对未来的规划目的很重要)。开发了基于铑的可植入自供电中子探测器,以获取外部和内部的中子通量分布。SPND沿着样品的中心纵轴植入,预计此处通量最低。伽马剂量率通过沿样品外表面移动的中子屏蔽石墨电离室获得。内部中子分布足够均匀,可对肝脏进行单次静态照射。为了进行剂量估算,设定辐照条件以便在健康组织中获得最大15 Gy - eq的剂量。此外,文献报道肿瘤中的硼浓度为47 ppm,健康组织中的硼浓度为8 ppm,并采用了更保守的关系(30/10 ppm)。为了对剂量进行保守估算,进行了以下考虑:i). 样本内部测得的最小中子通量(约5×10⁹ n cm⁻² s⁻¹)用于计算肿瘤中的剂量。(ii). 测得的最大中子通量(考虑内部和外部分布)用于计算健康组织中的剂量(约8.7×10⁹ n cm⁻² s⁻¹)。(iii). 测得的最大伽马剂量率(约13.5 Gy h⁻¹)用于肿瘤和健康组织。对于47 ppm的¹⁰B,肿瘤组织剂量约为69 Gy - eq,对于30 ppm,约为42 Gy - eq,健康组织中的最大剂量为15 Gy - eq。从这些结果可以看出,即使在最保守的情况下,从治疗角度来看最小肿瘤剂量也是可以接受的,这表明该设施的辐照条件对于提议的辐照具有相当好的特性。