Department of Physics and Atmospheric Science, Dalhousie University, Halifax, Nova Scotia, Canada.
Department of Diagnostic Imaging, Dalhousie University, Halifax, Nova Scotia, Canada.
Med Phys. 2018 Feb;45(2):934-942. doi: 10.1002/mp.12717. Epub 2017 Dec 25.
Radiopaque microspheres may provide intraprocedural and postprocedural feedback during transarterial radioembolization (TARE). Furthermore, the potential to use higher resolution x-ray imaging techniques as opposed to nuclear medicine imaging suggests that significant improvements in the accuracy and precision of radiation dosimetry calculations could be realized for this type of therapy. This study investigates the absorbed dose kernel for novel radiopaque microspheres including contributions of both short and long-lived contaminant radionuclides while concurrently quantifying the self-shielding of the glass network.
Monte Carlo simulations using EGSnrc were performed to determine the dose kernels for all monoenergetic electron emissions and all beta spectra for radionuclides reported in a neutron activation study of the microspheres. Simulations were benchmarked against an accepted Y dose point kernel. Self-shielding was quantified for the microspheres by simulating an isotropically emitting, uniformly distributed source, in glass and in water. The ratio of the absorbed doses was scored as a function of distance from a microsphere. The absorbed dose kernel for the microspheres was calculated for (a) two bead formulations following (b) two different durations of neutron activation, at (c) various time points following activation.
Self-shielding varies with time postremoval from the reactor. At early time points, it is less pronounced due to the higher energies of the emissions. It is on the order of 0.4-2.8% at a radial distance of 5.43 mm with increased size from 10 to 50 μm in diameter during the time that the microspheres would be administered to a patient. At long time points, self-shielding is more pronounced and can reach values in excess of 20% near the end of the range of the emissions. Absorbed dose kernels for Y, Y, Sr, Sr, Sr, Sr, Ga, Ga, and Si are presented and used to determine an overall kernel for the microspheres based on weighted activities. The shapes of the absorbed dose kernels are dominated at short times postactivation by the contributions of Ga and Ga. Following decay of the short-lived contaminants, the absorbed dose kernel is effectively that of Y. After approximately 1000 h postactivation, the contributions of Sr and Sr become increasingly dominant, though the absorbed dose-rate around the beads drops by roughly four orders of magnitude.
The introduction of high atomic number elements for the purpose of increasing radiopacity necessarily leads to the production of radionuclides other than Y in the microspheres. Most of the radionuclides in this study are short-lived and are likely not of any significant concern for this therapeutic agent. The presence of small quantities of longer lived radionuclides will change the shape of the absorbed dose kernel around a microsphere at long time points postadministration when activity levels are significantly reduced.
放射性微球在经动脉放射栓塞术(TARE)中可能提供术中及术后反馈。此外,与核医学成像相比,使用更高分辨率的 X 射线成像技术表明,这种治疗类型的辐射剂量计算的准确性和精密度可以得到显著提高。本研究调查了新型放射性微球的吸收剂量核,包括短寿命和长寿命污染物放射性核素的贡献,同时量化玻璃网络的自屏蔽。
使用 EGSnrc 进行蒙特卡罗模拟,以确定微球中子活化研究中报告的所有单能电子发射和所有β谱的剂量核。模拟结果与公认的 Y 剂量点核进行了基准测试。通过模拟各向同性发射、均匀分布的源,在玻璃中和水中,对微球的自屏蔽进行了量化。作为距离微球的函数,对吸收剂量进行评分。计算了微球的吸收剂量核(a)两种珠粒配方,(b)两种不同的中子活化持续时间,以及(c)在活化后的不同时间点。
自屏蔽随从反应堆中取出后的时间而变化。在早期,由于发射的能量较高,自屏蔽不那么明显。在直径为 10 至 50 μm 的微球施用于患者的时间内,在距微球 5.43 mm 的径向距离处,自屏蔽的大小为 0.4-2.8%。在长时间点,自屏蔽更为明显,在发射范围的末端附近可达到 20%以上的值。呈现了 Y、 Y、 Sr、 Sr、 Sr、 Sr、 Ga、 Ga 和 Si 的吸收剂量核,并用于基于加权活度确定微球的整体核。吸收剂量核的形状在短时间内主要由 Ga 和 Ga 的贡献决定。在短寿命污染物衰变后,吸收剂量核实际上是 Y。在大约 1000 小时的活化后, Sr 和 Sr 的贡献变得越来越重要,尽管珠粒周围的吸收剂量率下降了大约四个数量级。
为了增加放射性而引入高原子序数元素,必然会导致微球中产生除 Y 以外的放射性核素。本研究中的大多数放射性核素都是短寿命的,对于这种治疗剂不太可能有任何重大影响。当活性水平显著降低时,在施药后长时间点,少量长寿命放射性核素的存在会改变微球周围吸收剂量核的形状。