AB-BNCT 的诱导放射性:对全球不同设施的分析

M. Capoulat, A. J. Kreiner
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摘要

全球正在努力建立加速器硼中子俘获治疗(AB-BNCT)设施,其中涉及各种加速器技术和中子产生靶,每种技术和靶都具有不同的主射束特性及其产生的中子谱。为了实现长期可持续发展,必须尽可能减少残余放射性的产生,尤其是考虑到这些设备在医院环境中的预期用途。本文旨在定量评估这些设施中的残余放射性,同时考虑到一次活化和二次活化。一次活化主要产生于质子或氘核束与产生中子的靶的相互作用。二次活化则是暴露在中子通量下的元素发生中子诱导反应的结果,其中束流整形组件(BSA)是暴露最严重的组件。为了评估活化,我们评估了一组具有代表性的靶-BSA 配置。根据横截面数据和相应的靶材料计算了一次活化。中子活化利用 MCNP 6.1 代码进行蒙特卡罗模拟评估。关于靶活化,我们的研究结果表明,使用小于 10 MeV 质子的 9Be 靶是最清洁的选择,而使用质子的 7Li 靶则会导致最高的活化水平。至于 BSA 激活,中子能量是一个关键因素。就标准 BSA 材料而言,中子能量越高,产生放射性产物的潜在反应数量就越多。此外,我们的研究结果表明,合金材料中的杂质和次要成分引起的放射性不能忽略,必须在放射性计算中加以考虑。总之,本研究对常用靶和 BSA 材料的活化进行了全面分析,旨在从放射学角度为 AB-BNCT 设备的优化做出贡献。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Induced radioactivity in AB-BNCT: an analysis of the different facilities worldwide
The global effort to establish Accelerator-Based Boron Neutron Capture Therapy (AB-BNCT) facilities involves various accelerator technologies and neutron-producing targets, each characterized by different properties of the primary beam and neutron spectra they generate. With an emphasis on long-term sustainability, it is essential to minimize the production of residual radioactivity to the lowest possible level, particularly given their intended use in a hospital environment. This paper aims to quantitatively assess the residual radioactivity in these facilities, taking into account both primary and secondary activation. Primary activation primarily arises from the interaction of the proton or deuteron beam and the neutron-producing target. Secondary activation results from neutron-induced reactions on the elements exposed to the neutron flux, with the Beam Shaping Assembly (BSA) being the most exposed one. To assess activation, we evaluated a representative group of target-BSA configurations. Primary activation was calculated based on cross-sectional data and the corresponding target materials. Neutron activation was assessed using Monte Carlo simulations with the MCNP 6.1 code. Regarding target activation, our findings indicate that 9Be targets working with protons of less than 10 MeV represent the cleanest option, while 7Li targets working with protons lead to the highest activation levels. As for BSA activation, the neutron energy is a crucial factor. In the case of standard BSA materials, higher neutron energy results in an increased number of potential reactions that produce radioactive products. Additionally, our findings suggest that radioactivity induced by impurities and minor components in alloyed materials cannot be disregarded and must be taken into account in radioactivity calculations. In summary, this research provides a comprehensive analysis of activation of the commonly used targets and BSA materials, aimed at contributing to the optimization of AB-BNCT facilities from a radiological perspective.
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