Joubert Maria M, van Eeden Déte, du Plessis Freek C P
Department of Medical Physics, University of the Free State, Bloemfontein 9301, South Africa.
Biomed Phys Eng Express. 2021 Mar 1;7(3). doi: 10.1088/2057-1976/abe7c3.
. In this study, Monte Carlo (MC) simulations were done to relate the dose-response of the film to that in water. The effect of backscattering materials (PMMA, lead, polystyrene, and air) was investigated on its influence on film density for radionuclides including Am-241, Tc-99m, I-131, Cs-137.. A BEAMnrc MC simulation was designed to score a phase-space file (PSF) below the container of the radionuclide under consideration to use as an input file for the subsequent DOSXYZnrc MC simulation. The geometry of the container holding the radionuclide was built using the component modules available in BEAMnrc. BEAMDP was used to investigate the container effect on the radionuclide spectrum as well as the fluence. The DOSXYZnrc simulation produced the absorbed dose in XR-QA2 and RT-QA2 Gafchromicfilms. The DOSXYZnrc simulations were repeated for the Gafchromicfilm now replaced with water to get the absorbed dose in water. From these results, conversion factors for the dose in water to the film dose for the different radionuclides, Am-241, Tc-99m, I-131, and Cs-137 were obtained. The actual film dose was calculated using the specific gamma exposure constant (Γ) at a distance of 50 cm for a point source approximation. From the BEAMnrc simulations, the particle fluence was extracted from PSFs to correct for the fluence at 0.1 cm below the sources from the fluence 50 cm away since the inverse square law will not apply to finite-size sources. The absorbed dose profiles in the film were compared to the absorbed dose profiles from the MC simulations.. A fitting function based on the neutron depletion model fits the optical density versus absorbed film dose data well and can be used as a calibration tool to obtain the film dose from its optical density. Lead as a backscatter material results in a higher optical density change but a lower absorbed dose. The XR-QA2 Gafchromicfilm is more sensitive than the RT-QA2 Gafchromicfilm, showing a more responsive optical density (OD) change in the energy range of radionuclides used in this study. Conversion factors were determined to convert the dose in water to the dose in Gafchromicfilm. The Am-241 and I-131 simulated absorbed dose in the film to dose in water does not fluctuate as much as the simulated absorbed dose in film and water when using Tc-99m and Cs-137. Validation was shown for the comparison of the film and MC simulation absorbed dose profiles.. MC BEAMnrc simulations are useful to simulate radionuclides and their containers. BEAMDP extracted energy spectra showed that the radionuclide containers produced a Compton effect on the energy spectra and added filtration on the lower spectral photon components. Extracted fluence ratios from PSFs were used to calculate the absorbed dose value at 0.1 cm distance from the source. By using the fit function, the dose in the film can be determined for known optical density values. The effect of the backscatter materials showed that the XR-QA2 Gafchromicfilm results in higher optical density values than the RT-QA2 Gafchromicfilm. The absorbed dose in both the films is comparable but not for a radionuclide such as Am-241 with an activity of 74MBq. The lead backscatter material showed to be the most prominent in optical density enhancement, and the air equivalent material was the least prominent. The XR-QA2 Gafchromicfilm is the most sensitive and will be the best option if working with low energies. The absorbed dose in the XR-QA2 Gafchromicfilm also showed a good comparison to the absorbed dose in water for the Am-241 radionuclide with an activity of 74MBq. The absorbed dose in the films compares well to the MC simulated doses.
在本研究中,进行了蒙特卡罗(MC)模拟,以关联薄膜的剂量响应与水中的剂量响应。研究了反向散射材料(聚甲基丙烯酸甲酯、铅、聚苯乙烯和空气)对包括镅 - 241、锝 - 99m、碘 - 131、铯 - 137在内的放射性核素薄膜密度的影响。设计了一个BEAMnrc MC模拟,以在考虑的放射性核素容器下方对相空间文件(PSF)进行评分,用作后续DOSXYZnrc MC模拟的输入文件。使用BEAMnrc中可用的组件模块构建容纳放射性核素的容器的几何形状。BEAMDP用于研究容器对放射性核素能谱以及注量的影响。DOSXYZnrc模拟得出了XR - QA2和RT - QA2辐射变色薄膜中的吸收剂量。现在将辐射变色薄膜替换为水,重复进行DOSXYZnrc模拟,以得到水中的吸收剂量。根据这些结果,获得了不同放射性核素(镅 - 241、锝 - 99m、碘 - 131和铯 - 137)从水剂量到薄膜剂量的转换因子。实际薄膜剂量是使用点源近似在50 cm距离处的特定γ照射常数(Γ)计算得出的。从BEAMnrc模拟中,从PSF中提取粒子注量,以校正源下方0.1 cm处的注量与50 cm远处注量的差异(因为平方反比定律不适用于有限尺寸的源)。将薄膜中的吸收剂量分布与MC模拟的吸收剂量分布进行比较。基于中子耗尽模型的拟合函数能很好地拟合光密度与薄膜吸收剂量数据,可作为从光密度获取薄膜剂量的校准工具。铅作为反向散射材料会导致更高的光密度变化,但吸收剂量较低。XR - QA2辐射变色薄膜比RT - QA2辐射变色薄膜更敏感,在本研究中使用的放射性核素能量范围内显示出更明显的光密度(OD)变化。确定了将水剂量转换为辐射变色薄膜剂量的转换因子。当使用锝 - 99m和铯 - 137时,薄膜中镅 - 241和碘 - 131模拟的吸收剂量与水剂量的波动程度不如薄膜和水中模拟的吸收剂量波动程度大。展示了薄膜与MC模拟吸收剂量分布比较的验证。MC BEAMnrc模拟对于模拟放射性核素及其容器很有用。BEAMDP提取的能谱表明,放射性核素容器对能谱产生了康普顿效应,并在较低能谱光子成分上增加了过滤。从PSF中提取的注量比用于计算距源0.1 cm处的吸收剂量值。通过使用拟合函数,可以根据已知的光密度值确定薄膜中的剂量。反向散射材料的影响表明,XR - QA2辐射变色薄膜产生的光密度值高于RT - QA2辐射变色薄膜。两种薄膜中的吸收剂量相当,但对于活度为74MBq的镅 - 241等放射性核素并非如此。铅反向散射材料在光密度增强方面最为显著,而空气等效材料最不显著。XR - QA2辐射变色薄膜最敏感,如果处理低能量情况将是最佳选择。对于活度为74MBq的镅 - 241放射性核素,XR - QA2辐射变色薄膜中的吸收剂量与水中的吸收剂量也显示出良好的比较。薄膜中的吸收剂量与MC模拟剂量比较良好。