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关于在质子治疗中心使用230兆电子伏特质子回旋加速器作为硼中子俘获疗法的散裂中子源的可行性研究。

Feasibility study on the use of 230 MeV proton cyclotron in proton therapy centers as a spallation neutron source for BNCT.

作者信息

Nobakht E, Fouladi N

机构信息

Department of Nuclear Physics, University of Tabriz, Tabriz 51664, Iran.

出版信息

Rep Pract Oncol Radiother. 2019 Nov-Dec;24(6):644-653. doi: 10.1016/j.rpor.2019.10.005. Epub 2019 Oct 30.

Abstract

AIM

The feasibility of using 230 MeV proton cyclotrons in proton therapy centers as a spallation neutron source for Boron Neutron Capture Therapy (BNCT) was investigated.

BACKGROUND

BNCT is based on the neutron irradiation of a B-containing compound located selectively in tumor cells. Among various types of neutron generators, the spallation neutron source is a unique way to generate high-energy and high-flux neutrons.

MATERIALS AND METHODS

Neutron beam was generated by a proton accelerator via spallation reactions and then the produced neutron beam was shaped to be appropriate for BNCT. The proposed Beam Shaping Assembly (BSA) consists of different moderators, a reflector, a collimator, as well as thermal and gamma filters. In addition, the simulated Snyder head phantom was utilized to evaluate the dose distribution in tumor and normal tissue due to the irradiation by the designed beam. MCNPX2.6 Monte Carlo code was used to optimize BSA as well as evaluate dose evaluation.

RESULTS

A BSA was designed. With the BSA configuration and a beam current of 104 nA, epithermal neutron flux of 3.94 × 10 [n/cm] can be achieved, which is very low. Provided that we use the beam current of 5.75 μA, epithermal neutron flux of 2.18 × 10 [n/cm] can be obtained and the maximum dose of 38.2 Gy-eq can be delivered to tumor tissue at 1.4 cm from the phantom surface.

CONCLUSIONS

Results for 230 MeV protons show that with proposed BSA, proton beam current about 5.75 μA is required for this purpose.

摘要

目的

研究在质子治疗中心使用230 MeV质子回旋加速器作为硼中子俘获疗法(BNCT)的散裂中子源的可行性。

背景

BNCT基于对选择性位于肿瘤细胞中的含硼化合物进行中子辐照。在各种类型的中子发生器中,散裂中子源是产生高能和高通量中子的独特方式。

材料与方法

通过质子加速器经散裂反应产生中子束,然后将产生的中子束整形以适合BNCT。所提出的束流整形组件(BSA)由不同的慢化剂、反射器、准直器以及热和γ射线过滤器组成。此外,利用模拟的斯奈德头部体模评估设计束流辐照下肿瘤和正常组织中的剂量分布。使用MCNPX2.6蒙特卡罗代码优化BSA并评估剂量评估。

结果

设计了一个BSA。采用该BSA配置和104 nA的束流时,可实现3.94×10[n/cm]的超热中子通量,这非常低。如果使用5.75 μA的束流,则可获得2.18×10[n/cm]的超热中子通量,并且在距体模表面1.4 cm处可将最大剂量38.2 Gy-eq输送到肿瘤组织。

结论

230 MeV质子的结果表明,使用所提出的BSA,为此目的需要约5.75 μA的质子束流。

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