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Monte Carlo simulation of beta particle-induced bremsstrahlung doses

机译:凸起的β粒子诱导的Bremsstrahlung剂量的蒙特卡罗模拟

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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.
机译:众所周知,由β发射器产生的外部照射的保护比发射伽马辐射的放射源的相应屏蔽更简单。这是由不同材料中的相对强的吸收(即,短程)引起的。然而,对于强β来源,应特别注意源封装(基质)中诱导的Bremsstrahlung辐射,特别是对于具有核医学通常使用的具有相对高的β-终点能量(1MeV)的发射器。通过使用GEANT4软件,通过Monte Carlo Simulations研究了通过以下β发射器,SR-90(与其女儿Y-90),P-32和Bi-210一起生产的各种材料中的Bremsstrahlung光谱。在这些模拟中,假设点放射源被来自不同材料制成的圆柱形胶囊包围:Pb,Cu,Al,玻璃和塑料。对于圆柱铅和铝胶囊中Y-90(SR-90)的情况,这些胶囊的尺寸也已经变化。计算来自Bremsstrahlung辐射的吸收剂量率,用于封装点源从距水筒的表面置于30mm的距离,质量为75kg(大约代表人体)。在实验中还测量来自Y-90(SR-90)点源的Bremsstrahlung剂量和Bremsstrahlung光谱,并与相应的模拟结果进行比较。此外,在模拟中考虑使用Y-90的疗法中医务人员的Bremsstrahlung辐射风险,与手指剂量以及整体剂量在制备和注射该放射性同位素期间。对患者指定数量的Y-90申请进行了相应的年度剂量。

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