辐射防护 ›› 2026, Vol. 46 ›› Issue (3): 250-263.doi: 10.27045/j.1000-8187.202603008

• 医疗照射与防护 • 上一篇    下一篇

BNCT治疗脑胶质瘤剂量特性蒙特卡罗模拟研究

李波宁1, 王晓娟1, 方青龙1, 原林1, 王博宇1,2,3, 李茁1,2,3, 刘洋1,2,3   

  1. 1.西安工程大学 理学院,西安 710048;
    2.甘肃工业职业技术大学 核工程与技术学院,甘肃 天水 741025;
    3.甘肃省核工业机电研究所,甘肃 天水 741025
  • 收稿日期:2025-05-13 出版日期:2026-05-20 发布日期:2026-06-18
  • 通讯作者: 刘洋。E-mail:liuy@xpu.edu.cn
  • 作者简介:李波宁(1996—),男,现为西安工程大学凝聚态物理专业在读硕士研究生。E-mail:liboning@stu.xpu.edu.cn
  • 基金资助:
    陕西省教育厅重点科学研究计划项目(No.24JR071);西安工程大学青年骨干人才支持计划(107020688)。

Monte Carlo simulation study on dosimetry of BNCT treatment for glioma

LI Boning1, WANG Xiaojuan1, FANG Qinlong1, YUAN Lin1, WANG Boyu1,2,3, LI Zhuo1,2,3, LIU Yang1,2,3   

  1. 1. School of Science, Xi′an Polytechnic University,Xi′an 710048;
    2. College of Nuclear Engineering and Technology,Gansu Vocational University of Industry Technology, Gansu Tianshui 741025;
    3. Gansu Mechantronics Research Institute of Nuclear Industry, Gansu Tianshui 741025
  • Received:2025-05-13 Online:2026-05-20 Published:2026-06-18

摘要: 本文以西安脉冲反应堆中子源为基础,采用蒙特卡罗方法,对脑胶质瘤BNCT治疗中的束流整形组件(beam shaping assembly,BSA)设计及剂量特性开展了研究。在满足IAEA推荐束流指标的约束条件下,对慢化体、反射体、准直系统、热中子吸收体及γ吸收体等关键结构参数进行了优化,形成了以AlF3慢化体为核心的超热中子束流方案。进一步构建Snyder椭球脑模型及含肿瘤组织模型,计算并分析了不同硼浓度条件下硼俘获剂量、热中子剂量、快中子剂量及γ剂量的空间分布特征。结果表明,采用约60 cm的AlF3慢化体、约15 cm的Pb反射体、50 cm准直器、Gd热中子吸收体(0.3 cm/0.1 cm)及5 cm Bi γ吸收体的BSA组合,可获得满足治疗要求的超热中子通量;硼俘获剂量在肿瘤区形成显著峰值,并随硼浓度升高而逐渐增强,而非选择性剂量分量基本不受影响。通过总生物剂量评估,确定了不同硼浓度条件下的剂量率及相应治疗时间。上述结果为反应堆型BNCT束流设计及脑胶质瘤治疗的剂量优化提供了一定的数据支持。

关键词: 硼中子俘获治疗, 脑胶质瘤, 吸收剂量率, Snyder模型, 蒙特卡罗模拟

Abstract: In this study, based on the neutron source of the Xi′an Pulsed Reactor, Monte Carlo simulations were performed to systematically investigate the beam shaping assembly (BSA) design and dosimetric characteristics for BNCT treatment of brain glioma. Under the constraints of the beam quality criteria recommended by the IAEA, key components of the BSA—including the moderator, reflector, collimation system, thermal neutron absorber, and gamma filter—were optimized, resulting in an epithermal neutron beam configuration centered on an AlF3 moderator. Furthermore, a Snyder ellipsoidal head phantom and a corresponding tumor-bearing model were constructed to calculate and analyze the spatial distributions of boron capture dose, thermal neutron dose, fast neutron dose, and gamma dose under different boron concentrations. The results indicate that a BSA configuration consisting of an AlF3 moderator (~60 cm), a Pb reflector (~15 cm), a 50 cm collimator, Gd thermal neutron absorber (0.3 cm/0.1 cm), and a 5 cm Bi gamma filter can provide an epithermal neutron flux that satisfies therapeutic requirements. A pronounced peak of boron capture dose is formed within the tumor region and increases significantly with increasing boron concentration, while the non-selective dose components remain essentially unchanged. Based on the evaluation of the total biologically weighted dose, the corresponding dose rates and treatment times for different boron concentrations were determined. These results provide a reliable theoretical basis for reactor-based BNCT beam design and dosimetric optimization in the treatment of brain glioma.

Key words: boron neutron capture therapy, glioma, absorbed dose rate, snyder model, Monte Carlo simulation

中图分类号: 

  • TL99