Study on Hyper Thermal Neutron Irradiation Field for Neutron Capture Therapy

中子俘获治疗的超热中子辐照场研究

• 批准号: 08458125
• 负责人: KOBAYASHI Tooru
• 金额: $ 4.54万
• 依托单位: KYOTO UNIVERSITY
• 依托单位国家: 日本
• 项目类别: Grant-in-Aid for Scientific Research (B)
• 财政年份: 1996
• 资助国家: 日本
• 起止时间: 1996 至 1997
• 项目状态: 已结题
• 来源: https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-08458125/
• 关键词: Neutron Capture Therapy; Hyper Thermal Neutron; High Temperature Scatterer; Graphite; Beryllium; Zirconium Hydride; 中性子捕捉療法

The purpose of this research is to clarify the irradiation characteristics of hyper-thermal neutrons for a living body, and the feasibility of hyper thermal neutron irradiation field, by experiments and simulation calculations.In 1996 (Heisei 8), a "test-type" hyper-thermal neutron generator was designed from the results of the basic researches mainly with simulation calculations, and the "high-temperature scatterer" part was assembled. The design goal of this generator was that the attainable maximum temperature was almost 1200 degrees centigrade (1500K). From the standing-point of safety first at high-temperature experiments, stainless steal, which has good characteristics of heat-proof and corrosion-proof, was selected as main material of the structural frame. The electric heating using molybdenum high-temperature heaters, the heat remove by molybdenum heat reflectors, and the heat measurement by R-type thermo-couples were applied. Graphite scatterer was selected because of its stab … More ility at high temperature. The scatterer is possible to be replaced with the other scatterer.In 1997 (Heisei 9), the "controller" part was made and combined with the high-temperature scatterer part, and finally, the generator was completed. Before the employment of the generator at neutron irradiation field, the heating tests were performed. From the test results, it was confirmed that the scatterer maximum temperature was attainable to be 1200 degrees centigrade, and that there was no problem for thermal stability, thermal controllability and safety at the high temperature employment. As one of the experiments for the characteristics estimation, the neutron energy spectrum dependent on the scatterer temperature was estimated by TOF (time of flight) method using the LINAC (Electron Linear Accelerator) neutron generator at KURRI (Kyoto University Research Reactor Insitute). The estimation by simulation calculations were also performed. From the experiment and calculation results, it was confirmed that the neutron temperature shifted to be higher according to the scatterer temperature.At present, phantom experiment at the KUR (Kyoto University Reactor) Heavy Water Facility are planning in order to estimate the neutron dose distribution in a living body, on the assumption of the application of hyper-thermal neutrons irradiation to actual NCT. Less

这项研究的目的是通过实验和仿真计算来阐明活体高热中子的辐射特征，以及过度热中性辐射领域的可行性。1996年（Heisei 8），“测试型”过度的中子生成器是从基本研究的结果中设计了一个基本的散布，并散布了较高的散布。该发电机的设计目标是可达到的最高温度接近1200度（1500K）。从高温实验的安全性首先站立起点，不锈钢被选为结构框架的主要材料，具有良好的耐热和耐腐蚀性的特征。使用钼高温加热器的电加热，通过钼热反射器去除热量，并使用R型热夫妻进行热量测量。之所以选择石墨散射器，是因为其刺伤……在高温下更具可行性。散点子可以用另一个散射器代替。在1997年（Heisei 9），“控制器”部分是制造并与高温散射器部分合并的，最后，发电机完成了。在中子辐照场的发电机员工之前，进行了加热测试。从测试结果中可以证实，散射器的最高温度可以达到1200度，并且在高温就业时的热稳定性，热控制和安全性没有问题。作为特征估计的实验之一，使用LINAC（京都大学研究反应堆INSTUTE）的Linac（电子线性加速器）中子发生器，通过TOF（飞行时间）方法估算了取决于散射体温度的中子能谱。还进行了模拟计算的估计。从实验和计算结果中，可以证实，根据散点剂的温度，中子温度转移到更高。在目前，KUR（京都大学反应堆）重水设施的幻象实验正在计划，以估计活体中的中子剂量分布，假设应用于高热中性中含量中性中含量的实际Ncradiation nctacriation Nctct。较少的