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用于硼中子俘获治疗领域的HANARO中子辐照设施的发展与特性

Development and characteristics of the HANARO neutron irradiation facility for applications in the boron neutron capture therapy field.

作者信息

Kim Myong-Seop, Lee Byung-Chul, Hwang Sung-Yul, Kim Heonil, Jun Byung-Jin

机构信息

Korea Atomic Energy Research Institute, 150 Deokjin-Dong, Yuseong, Daejeon 305-353, Korea.

出版信息

Phys Med Biol. 2007 May 7;52(9):2553-66. doi: 10.1088/0031-9155/52/9/015. Epub 2007 Apr 17.

Abstract

The HANARO neutron irradiation facility for various applications in the boron neutron capture therapy (BNCT) field was developed, and its characteristics were investigated. In order to obtain the sufficient thermal neutron flux with a low level of contamination by fast neutrons and gamma rays, a radiation filtering method was adopted. The radiation filter was designed by using a silicon single crystal, cooled by liquid nitrogen, and a bismuth crystal. The installation of the main components of the irradiation facility and the irradiation room was finished. Neutron beam characteristics were measured by using bare and cadmium-covered gold foils and wires. The in-phantom neutron flux distribution was measured for flux mapping inside the phantom. The gamma-ray dose was determined by using TLD-700 thermoluminescence dosimeters. The thermal and fast neutron fluxes and the gamma-ray dose were calculated by using the MCNP code, and they were compared with experimental data. The thermal neutron flux and Cd ratio available at this facility were confirmed to be 1.49 x 10(9) n cm(-2) s(-1) and 152, respectively. The maximum neutron flux inside the phantom was measured to be 2.79 x 10(9) n cm(-2) s(-1) at a depth of 3 mm in the phantom. The two-dimensional in-phantom neutron flux distribution was determined, and significant neutron irradiation was observed within 20 mm from the phantom surface. The gamma-ray dose rate for the free beam condition was expected to be about 80 cGy h(-1). These experimental results were reasonably well supported by calculation using the facility design code. This HANARO thermal neutron facility can be used not only for clinical trials, but also for various pre-clinical studies in the BNCT field.

摘要

开发了用于硼中子俘获疗法(BNCT)领域各种应用的HANARO中子辐照设施,并对其特性进行了研究。为了在快中子和伽马射线污染水平较低的情况下获得足够的热中子通量,采用了一种辐射过滤方法。辐射过滤器采用液氮冷却的硅单晶和铋晶体进行设计。辐照设施和辐照室的主要部件安装完成。使用裸金箔和镉覆盖的金箔及金线测量了中子束特性。测量了模体内部的中子通量分布以进行通量映射。使用TLD - 700热释光剂量计确定了伽马射线剂量。使用MCNP代码计算了热中子通量、快中子通量和伽马射线剂量,并与实验数据进行了比较。该设施的热中子通量和镉比分别确定为1.49×10⁹ n cm⁻² s⁻¹和152。模体内部的最大中子通量在模体深度3 mm处测量为2.79×10⁹ n cm⁻² s⁻¹。确定了模体内部二维中子通量分布,并且在距模体表面20 mm范围内观察到了显著的中子辐照。自由束条件下的伽马射线剂量率预计约为80 cGy h⁻¹。这些实验结果通过使用设施设计代码进行的计算得到了合理的良好支持。这个HANARO热中子设施不仅可用于临床试验,还可用于BNCT领域的各种临床前研究。

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