基于加速器的蒙特卡罗方法在放射性材料99Mo/999mTc生产替代品中的应用:核医学中的科学便利性考虑

IF 1 Q4 MATHEMATICS, INTERDISCIPLINARY APPLICATIONS
A. Khorshidi
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引用次数: 18

摘要

一些加速器技术已经用于商业[公式:见正文]Mo-99mTc生产,因为经济标准被认为代表了包括加速器和反应器在内的各种技术之间的主要差异。本研究综述了使用传统医疗设施生产钼的已知和潜在[配方:见正文]。使用18[公式:见正文]MeV质子束模拟通过[公式:参见正文],[公式:详见正文]直接反应在[公式:请见正文]Mo上产生99mTc的基于加速器的方法。同时,当使用加速器的35[公式:见文本]MeV的电子源时,研究了通过[公式:见图文本]Mo([公式:参见文本])[公式:看文本]Mo和[公式:看看文本]Mo的间接[公式:看到文本]Mo反应的概念设计。这些间接反应是通过在铅区内不同位置插入[公式:见正文]Mo样品来探索的。此外基于质子加速器的绝热共振穿越(ARC)方法,通过[公式:见正文]Mo中的嬗变([公式:参见正文]Mo在30[公式:详见正文]使用MeV质子束。使用所提出的替代方法研究饱和活性和产率。与加速器锝生产相关的潜在增殖风险是最小的。虽然加速器可以转化为中子源,进而用于辐照[公式:见正文]U以培育钚,而用于浓缩[公式:见正文]目标钼的离心机可以转化为浓缩铀,但这将导致全球生产能力非常小,特别是与研究或动力反应堆相比。新方法的潜力可以为各种放射性同位素生产目的提供替代或补充目前基于反应堆的供应源。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Accelerator-Based Methods in Radio-Material 99Mo/99mTc Production Alternatives by Monte Carlo Method: The Scientific-Expedient Considerations in Nuclear Medicine
Some accelerator technologies are already used for commercial [Formula: see text]Mo-99mTc production, as the economic criteria are considered representative of the main differences between diverse technologies including accelerators and reactors. This study has provided a review of known and potential [Formula: see text]Mo production using conventional medical facilities. Accelerator-based method in 99mTc production via ([Formula: see text], [Formula: see text]) direct reaction on [Formula: see text]Mo was simulated using 18[Formula: see text]MeV proton beam. Meanwhile, a conceptual design for indirect [Formula: see text]Mo production via [Formula: see text]Mo([Formula: see text])[Formula: see text]Mo and [Formula: see text]Mo(n,[Formula: see text]2n)[Formula: see text]Mo reactions was investigated when an electron source of 35[Formula: see text]MeV by accelerator is used. These indirect reactions were explored via inserted [Formula: see text]Mo samples at different positions inside the lead region. Furthermore, Adiabatic Resonance Crossing (ARC) method based on proton accelerator via transmutation in [Formula: see text]Mo([Formula: see text]Mo was examined when the 30[Formula: see text]MeV proton beam is used. Saturation activity and yield were investigated using alternative proposed methods. The potential proliferation risk associated with accelerator technetium production is minimal. While accelerators could be turned into neutron sources which could in turn be used to irradiate [Formula: see text]U to breed plutonium, and centrifuges used to enrich [Formula: see text]Mo for targets could conceivably be turned to enriching uranium, this would result in very tiny global production capability particularly compared with research or power reactors. The potential of the fresh methods could provide a replacement or complement over current reactor-based supply sources in various radioisotopes production purposes.
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来源期刊
Journal of Multiscale Modelling
Journal of Multiscale Modelling MATHEMATICS, INTERDISCIPLINARY APPLICATIONS-
CiteScore
2.70
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0.00%
发文量
9
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