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设计用于硼中子俘获治疗的基于加速器的超热中子束。

Designing accelerator-based epithermal neutron beams for boron neutron capture therapy.

作者信息

Bleuel D L, Donahue R J, Ludewigt B A, Vujic J

机构信息

E. O. Lawrence Berkeley National Laboratory, Berkeley, California 94720, USA.

出版信息

Med Phys. 1998 Sep;25(9):1725-34. doi: 10.1118/1.598353.

Abstract

The 7Li(p,n)7Be reaction has been investigated as an accelerator-driven neutron source for proton energies between 2.1 and 2.6 MeV. Epithermal neutron beams shaped by three moderator materials, Al/AlF3, 7LiF, and D2O, have been analyzed and their usefulness for boron neutron capture therapy (BNCT) treatments evaluated. Radiation transport through the moderator assembly has been simulated with the Monte Carlo N-particle code (MCNP). Fluence and dose distributions in a head phantom were calculated using BNCT treatment planning software. Depth-dose distributions and treatment times were studied as a function of proton beam energy and moderator thickness. It was found that an accelerator-based neutron source with Al/AlF3 or 7LiF as moderator material can produce depth-dose distributions superior to those calculated for a previously published neutron beam design for the Brookhaven Medical Research Reactor, achieving up to approximately 50% higher doses near the midline of the brain. For a single beam treatment, a proton beam current of 20 mA, and a 7LiF moderator, the treatment time was estimated to be about 40 min. The tumor dose deposited at a depth of 8 cm was calculated to be about 21 Gy-Eq.

摘要

已对7Li(p,n)7Be反应作为质子能量在2.1至2.6 MeV之间的加速器驱动中子源进行了研究。分析了由三种慢化剂材料Al/AlF3、7LiF和D2O形成的超热中子束,并评估了它们在硼中子俘获疗法(BNCT)治疗中的效用。使用蒙特卡罗N粒子代码(MCNP)模拟了通过慢化剂组件的辐射传输。使用BNCT治疗计划软件计算了头部模型中的注量和剂量分布。研究了深度剂量分布和治疗时间作为质子束能量和慢化剂厚度的函数。结果发现,以Al/AlF3或7LiF作为慢化剂材料的基于加速器的中子源能够产生比先前为布鲁克海文医学研究反应堆公布的中子束设计所计算的深度剂量分布更好的分布,在脑中线附近实现高达约50%的更高剂量。对于单束治疗、20 mA的质子束电流和7LiF慢化剂,估计治疗时间约为40分钟。计算得出在8 cm深度处沉积的肿瘤剂量约为21 Gy-Eq。

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