Allen D A, Beynon T D
School of Physics and Space Research, University of Birmingham, Edgbaston, UK.
Phys Med Biol. 1995 May;40(5):807-21. doi: 10.1088/0031-9155/40/5/007.
An achievable design concept for a boron neutron capture therapy (BNCT) facility, based on a high-current, low-energy proton accelerator, is described. Neutrons are produced within a thick natural lithium target, under bombardment from protons with an initial energy between 2.5 and 3.0 MeV. The proton current will be up to 10 mA. After gamma-ray filtering, the neutrons are partially moderated to epithermal energies within a heavy-water moderator, poisoned with 6Li to remove thermal neutrons. Monte Carlo modelling has been used to predict system performance in terms of neutron fluence rate and neutron and gamma-ray dose at the patient position. The relationship between the system performance and key parameters, such as proton energy, moderator depth and 6Li concentration, has been investigated. With a proton current of 10 mA, the facility is capable of providing a therapy beam with a useful neutron fluence rate of 10(9) cm-2 s-1 and a neutron dose per unit fluence of less than 6 x 10(-13) Gy cm2, with a gamma-ray contamination of the therapy beam of about 10(-13) Gy cm2.
本文描述了一种基于高电流、低能量质子加速器的硼中子俘获疗法(BNCT)设施的可行设计概念。在初始能量为2.5至3.0 MeV的质子轰击下,在厚天然锂靶内产生中子。质子电流将高达10 mA。经过伽马射线过滤后,中子在重水慢化剂中部分慢化为超热能量,重水慢化剂中含有6Li以去除热中子。蒙特卡罗模拟已用于预测患者位置处的中子注量率以及中子和伽马射线剂量方面的系统性能。已研究了系统性能与质子能量、慢化剂深度和6Li浓度等关键参数之间的关系。当质子电流为10 mA时,该设施能够提供有用中子注量率为10(9) cm-2 s-1且每单位注量的中子剂量小于6×10(-13) Gy cm2的治疗束,治疗束的伽马射线污染约为10(-13) Gy cm2。