Impact of neutron sieve therapy for deep site in boron neutron capture therapy using Monte Carlo calculation.

IF 0.8 4区 环境科学与生态学 Q4 ENVIRONMENTAL SCIENCES
Keiichiro Matsushita, Hideya Yamazaki, Hiroaki Matsubara
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引用次数: 0

Abstract

Recent Boron neutron capture therapy (BNCT) has shifted to accelerator-based systems. One of them is a compact neutron generator developed using silicon carbide (SiC) semiconductors by Fukushima SiC Applied Technology Co. However, neutron penetration remains a critical challenge for treating deep-seated tumors. This study investigated the potential of neutron sieve therapy, originally developed to enhance the depth dose distribution in X-ray therapy, to improve BNCT dose distribution via Monte Carlo simulations based on the Fukushima SiC BNCT system. Dose distribution changes were investigated using polyethylene and 6LiF-plastic in block and sieve shapes. The results show that the maximum thermal neutron fluence depth was shallower (deeper) with polyethylene (6LiF-plastic) filters. The sieve filter moderately altered the dose distribution compared to the block filter due to density differences. The maximum dose point shifted 8 mm deeper using a sieve filter composed of 6LiF-plastic and polyethylene, with a 5.5% increase at 20 mm depth in neutron fluence at the same skin dose.

用蒙特卡罗计算中子筛治疗对硼中子俘获治疗中深部部位的影响。
最近的硼中子捕获疗法(BNCT)已经转向基于加速器的系统。其中之一是由福岛碳化硅应用技术有限公司开发的使用碳化硅(SiC)半导体的紧凑型中子发生器。然而,中子穿透仍然是治疗深部肿瘤的关键挑战。基于福岛碳化硅BNCT系统,本研究通过蒙特卡罗模拟研究了中子筛治疗(最初用于增强x射线治疗中的深度剂量分布)改善BNCT剂量分布的潜力。用聚乙烯和6liff塑料以块状和筛状考察了剂量分布的变化。结果表明,聚乙烯(6liff -塑料)过滤器的最大热中子通量深度较浅(较深);由于密度差异,筛子过滤器与块过滤器相比适度改变了剂量分布。使用由6liff塑料和聚乙烯组成的筛子过滤器时,最大剂量点更深移动了8mm,在相同皮肤剂量下,20 mm深度的中子通量增加了5.5%。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Radiation protection dosimetry
Radiation protection dosimetry 环境科学-公共卫生、环境卫生与职业卫生
CiteScore
1.40
自引率
10.00%
发文量
223
审稿时长
6-12 weeks
期刊介绍: Radiation Protection Dosimetry covers all aspects of personal and environmental dosimetry and monitoring, for both ionising and non-ionising radiations. This includes biological aspects, physical concepts, biophysical dosimetry, external and internal personal dosimetry and monitoring, environmental and workplace monitoring, accident dosimetry, and dosimetry related to the protection of patients. Particular emphasis is placed on papers covering the fundamentals of dosimetry; units, radiation quantities and conversion factors. Papers covering archaeological dating are included only if the fundamental measurement method or technique, such as thermoluminescence, has direct application to personal dosimetry measurements. Papers covering the dosimetric aspects of radon or other naturally occurring radioactive materials and low level radiation are included. Animal experiments and ecological sample measurements are not included unless there is a significant relevant content reason.
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