Mrdja D, Bikit K, Bikit I, Slivka J, Forkapic S, Knezevic J
University of Novi Sad, Faculty of Sciences, Department of Physics, Trg Dositeja Obradovica 4, 21000 Novi Sad, Serbia.
J Radiol Prot. 2018 Mar;38(1):34-47. doi: 10.1088/1361-6498/aa928f. Epub 2017 Oct 11.
It is well known that protection from the external irradiation produced by beta emitters is simpler than the corresponding shielding of radioactive sources that emit gamma radiation. This is caused by the relatively strong absorption (i.e. short range) of electrons in different materials. However, for strong beta sources specific attention should be paid to the bremsstrahlung radiation induced in the source encapsulation (matrix), especially for emitters with relatively high beta-endpoint energy (1 MeV) that are frequently used in nuclear medicine. In the present work, the bremsstrahlung spectra produced in various materials by the following beta emitters, Sr-90 (together with its daughter Y-90), P-32 and Bi-210, were investigated by Monte Carlo simulations using Geant4 software. In these simulations, it is supposed that the point radioactive sources are surrounded by cylindrically shaped capsules made from different materials: Pb, Cu, Al, glass and plastic. For the case of Y-90(Sr-90) in cylindrical lead and aluminum capsules, the dimensions of these capsules have also been varied. The absorbed dose rates from bremsstrahlung radiation were calculated for cases where the encapsulated point source is placed at a distance of 30 mm from the surface of a water cylinder with a mass of 75 kg (approximately representing the human body). The bremsstrahlung dose rate and bremsstrahlung spectrum from the Y-90(Sr-90) point source encapsulated in an Al capsule were also measured experimentally and compared with the corresponding simulation results. In addition, the bremsstrahlung radiation risk for medical staff in therapies using Y-90 was considered in simulations, relating to finger dose as well as whole-body dose during preparation and injection of this radioisotope. The corresponding annual doses were obtained for medical workers for specified numbers of Y-90 applications to patients.
众所周知,防护β发射体产生的外部辐射比防护发射γ辐射的放射性源的相应屏蔽要简单。这是由于电子在不同材料中的吸收相对较强(即射程较短)所致。然而,对于强β源,应特别注意源封装(基体)中产生的轫致辐射,特别是对于核医学中常用的具有相对较高β端点能量(1 MeV)的发射体。在本工作中,使用Geant4软件通过蒙特卡罗模拟研究了以下β发射体Sr-90(及其子体Y-90)、P-32和Bi-210在各种材料中产生的轫致辐射谱。在这些模拟中,假设点放射源被由不同材料制成的圆柱形胶囊包围:铅、铜、铝、玻璃和塑料。对于圆柱形铅和铝胶囊中的Y-90(Sr-90)情况,这些胶囊的尺寸也有所变化。对于封装的点源放置在距质量为75 kg的水缸表面30 mm处(近似代表人体)的情况,计算了轫致辐射的吸收剂量率。还对封装在铝胶囊中的Y-90(Sr-90)点源的轫致辐射剂量率和轫致辐射谱进行了实验测量,并与相应的模拟结果进行了比较。此外,在模拟中考虑了使用Y-90进行治疗时医护人员的轫致辐射风险,涉及制备和注射这种放射性同位素期间的手指剂量以及全身剂量。针对给患者使用特定数量Y-90的情况,获得了医护人员相应的年剂量。